Text

Amends 119 & 111 to Licenses NPF-2 & NPF-8,respectively, Replacing Requirements Associated W/Control Room Emergency Ventilation Sys Contained in TS Section 3/4.7.7 W/ Requirements Re Operation of Control Room Emergency
	ML20112C071
Person / Time
Site:	Farley
Issue date:	05/21/1996
From:	Berkow H; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20112C073	List: ML20112C071; ML20112C075;
References
	NUDOCS 9605240157
	Download: ML20112C071 (18)
	v • d • e

,-!

' p acer p-t UNITED STATES g

j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20086 4001

\\...../

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.119 License No. NPF-2 1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated December 19, 1995, as supplemented by letters dated January 5, 1996 and May 3, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and j

regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this license amendment will not be inimical to the 1

common defense and security or to the health and safety of the public; and E.

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

2.

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

NPF-2 is hereby amended to read as follows:

1 9605240157 960521 PDR ADOCK 05000348 P

PDR

. (2)

Technical Specifications The Technical Specifications contained in Ap)endices A and B, as revised through Amendment No. 119, are here)y incorporated in the license.

Southern Nuclear shall operate the facility in acccrdance with the Technical Specifications.

3.

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

T E NUCLEAR REGULATORY COMMISSION O

I uIK(

i erbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation j

Attachment:

1 Changes to the Technical Specifications Date of Issuance:

May 21, 1996

4 ATTACHMENT TO LICENSE AMENDMENT NO.119 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Paaes Insert Paaes 3/4 7-16 3/4 7-16 3/4 7-17 3/4 7-17 3/4 7-17a 3/4 7-17a 3/4-7-17b B 3/4 7-4 B 3/4 7-4 B 3/4 7-4a l

l

PLANT SYSTEMS l

3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM l

CONTROL ROOM EMERGENCY FILTRATION / PRESSURIZATION SYSTEM (CREFS) l

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

i APPLICABILITY:

ALL MODES, during movement of irradiated fuel assemblies, j

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 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 .

MODES 5, 6, during movement of irradiated fuel assemblies, and during movement of loads over irradiated fuels a.

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

I b.

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

I SURVEILLANCE REQUIRFRENTS 4.7.7.1 Each CREFS train shall be demonstrated OPERABLE:

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

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

l l

A one-time extension to 30 days for each train of the recirculation filtration function of CREFS is granted for implementation of control room cooling design changes. The provisions of specification 3.0.4 are not applicable during this 30-day extension. This one-time extension expires on completion of the Unit 1 14th refueling outage (Spring '97).

FARLEY-UNIT 1 3/4 7-16 AMENDMENT NO119 l l

qi PLANT SYSTEMR l

l SURVEILLANCE RECUIREMENTS (Continued) b.

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

maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release that could have contamina*ed the charcoal adsorbers er "2FA filters in any ventilation zone ec municating witn 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 esrbon adsorber section leak test in accordance with Section 5 of ANSI N510-1980.

(b)

An in-place DOP test for the HEPA filters shall be performed in accordance with Section 10 of ANSI N510-i 1980.

1 (c)

A charcoal.adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall be performed in accordance with Section 12 of ANSI N510-1980.

2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon santple obtained in accordance with Section 13 of ANSI N510-1980 meets the j

laboratory testing efficiencies criteria given in Note 2 j

when tested with methyl iodide at 80'C and 70% relative humidity.

3.

Verifying a system flow rate as indicated in Note 1 during system operation when tested in accordance with Section 8 of ANSI N510-1960.

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 Section 13 of ANSI N510-1980 meets the laboratory testing ef ficiencies criteria given in Note 2 when tested with methyl iodide at 80*C and 70% relative humidity.

4 FARLEY-UNIT 1 3/4 7-17 AMENDMENT NO.119 i

\\

i

.qq PLANT SYSTEMS L

SURVEI', LANCE REQUIREMENTS (Continued) m.. - -

d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and enarcoal adsorber bar.ks is less than 6 inches Water Gauge 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.8 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 Section 14 of ANSI N510-1980.

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 Section 10 of ANSI N510-1980 while operating the system at a flow rate indicated in Nete 1.

f.

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

or equal to 99.5% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with Section 12 of ANSI N510-1980 while operating the system at a flow rate indicated in Note 1.

Note 1.

a.

Control Room Recirculation Filter Unit 2000 cfm t 10%

b.

Control Room Filter Unit 1000 cfm 2 10%

c.

Control Room Pressurization Filter Unit 300 cfm 2 10%

Note 2.

a.

Control Room Recirculation Filter Unit 2 99%

b.

Control Room Filter Unit 2 99%

c.

Control Room Pressurization 2 99.825%

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

l FARLEY-UNIT 1 3/4 7-17a AMENDMENT NO.11h

PLANT SYSTEMS 3/4.7.7 Cu-i GL arm u m "CY VENTIIavION SYSTEM COWL ROCE AIR CONDITIONING SYSTEM f CRACS)

LIMITING 00NDITION POR OPERATION 3.7.7.2 Two control Room Air Conditioning System (CRACS) 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 CRACS train inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 fuels a.

With one CRACS train inoperable, restore the inoperable system to OPERABLE status within 30 days or lassediately place the OPERABLE CRACS train in operation or immediately suspend movement of irradiated fuel assemblies and movement of loads over irradiated

fuel, b.

With two CRACS trains inoperable, insediately suspend movement of irradiated fuel assemblies and movement of loads over irradiated fuel.

SURVEILLANCE REQUIREMENTS 4.7.7.2 At least once per 18 monthe verify that each CRACS train has the capability to remove the assumed heat loads.

The provisions of specification 3.0.4 are not applicable during the initial 30 days of implementation of control room cooling design changes.

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

119

, :g r

'YSTEM'S PLANT S

BASES 3/4 7.6.1 ULTIMATE HEAT SINK (RIVER) 1 This specification deleted.

l_4

'.6.2 ULTIMATE HEAT SINK (PONO) l l

The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal j

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 cased 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.

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 preerurize the control room.

The OPERABILITY of this system in conjunction with control room design provisiens 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 period of time period, and ability of the remaining train to provide the required capability, i

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 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 y

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

FARLEY-UNIT -

B 3/4 7-4 AMENDMENT NO.

119 1

\\

4 I

PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM EMEROENCY VENTILATION SYSTEM f corit irued )

With one CRAC train inoperable, the inoperable train..ust be returned to OFERABLE 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 assemblies and movement of loads over irradiated fuel.

The OPERABILITY of the control room emergency ventilation system ensures that l

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 temain habitable for operations personnel during and following all credible accident conditions.

3/4.7.8 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM (PENETRATION ROOM AIR FILTRATION SYSTEM)

The OPERABILITY of the penetration room air filtration system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.

t l

Cumulati"e operation of the system with the heaters & for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

]

)

FARLEY-UNIT 1 B 3/4 7-da AMENDMENT NO.j j g I i

/

(

ag-

,#* "%,4 UNITED STATES p

4 g

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4001 49.....,o l

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.111 License No. NPF-8 l

1.

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

A.

The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated December 19, 1995, as supplemented by letters dated January 5, 1996 and May 3, 1996,

omplies with the standards and requirements of the Atomic Energy l

Act of 1954, as amended (the Act), and the Comission's rules and l

regulations set forth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; i

i C.

There is reasonable assurance (i) that the activities authorized l

by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; i

l D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the j

public; and E.

The issuance of this amendment is in accoroTnce with 10 CFR Part 51 of the Comission's regulations and.11 applicable i

requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-8 is hereby amended to read as follows:

9

c'.

, (2)

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 111, are hereby incorporated in the license.

Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

I 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION He ert N. Berkow, Director Project Directorate II-2 l

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 21, 1996 1

s. sj ATTACHMENT TO LICENSE AMENDMENT N0.111 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET N0 50-364 1

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Remove Paaes Insert Paaes 3/4 7-16 3/4 7-16 3/4 7-17 3/4 7-17 3/4 7-17a 3/4 7-17a 3/4 7-17b B 3/4 7-4 8 3/4 7-4 B 3/4 7-4a i

e

PLANT SYSTEMS 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM CONTROL ROOM EMERGENCY FILTRATION / PRESSURIZATION SYSTEM (CREFS) l LIMITING CONDITION FOR OPERATION 3.7.7.1 Two Control Room Emergency Filtration / Pressurization System (CREFS) trains shall be OPERABLE.

APPLICABILITY:

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

1 ACTION:

1 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 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:

I 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 CREFS train shall be demonstrated OPERABLE:

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

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

i

A one-time extension to 30 days for each train of the recirculation

, filtration function of CREFS is granted for implementation of control room cooling design changes. The provisions of specification 3.0.4 are not applicable during this 30-day extension.

This one-time extension expires on completion of the Unit 1 14th refueling outage (Spring '97).

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

l

' Sh PLANT SYSTEMS l'

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 HFF* filters in a.ny ventilation zone communicating with. - syatem by:

l l

1.

Verifying that the cleanup system satisfies the in-place i

testing acceptance criteria of greater than or equal to l

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 carben adsorber section leak test in accordance with Section 5 of ANSI N510-1980.

(b)

An in-place DOP test for the HEPA filters shall be performed in accordance with Section 10 of ANSI N510-1980.

l (c)

A charcoal adsorber section leak test with a gaseous halogenated hydrocarbon refrigerant shall be performed in accordance with Section 12 of ANSI N510-1980.

2.

Verifying within 31 days after removal that a laboratory l

analysis of a representative carbon sample obtained in accordance with Section 13 of ANSI N510-1980 meets the laboratory testing efficiencies criteria given in Note 2 when tested with methyl iodide at 80*C and 70% relative humidity.

3.

Verifying a system flow rate as indicated in Note 1 during system operation when tested in accordance with Section 8 of ANSI N510-1980.

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 analysis of a representative carbon sample obtained in I

accordance with Section 13 of ANSI N510-1980 meets the I

laboratory testing efficiencies criteria given in Note 2 when tested with methyl iodide at 80*C and 70% relative humidity.

I FARLEY-UNIT 2 3/4 7-17 AMENDMENT NO.111 l

sa.

I

' PLANT SYSTEM 9 i

SURVEILLANCE REQUIREMENTS (Continued) d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA f'; ers and charcoal adsorber ta,- is less than 6 inches Water Gauge while operating the system at a ficw 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 i

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 0.8 kw when tested in accordance with Section 14 of ANSI N510-1980.

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 Section 10 of ANSI N510-1980 while operating 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 are tested in-place in accordance with Section l'2 of j

ANSI N510-1980 while operating the system at a flow rate indicated in Note 1.

Note 1.

a.

Control Room Recirculation Filter Unit 2000 cfm 10%

i l

b.

Control Room Filter Unit 1000 cfm 2 10%

c.

Control Room Pressurization Filter Unit 3:3 cfm 10%

Note 2.

a.

Control Room Recirculation Filter Unit 2 99%

b.

Control Room Filter Unit 2 99%

)

c.

Control Room Pressurization 2 99.825%

l I

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

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

l 111

PLANT SYSTEMS 3/4.7.7 CG i GL ROOM EMrprieuCY VENTILATION SYSTEM CONTROL ROCM AIR CONDITIONING SYSTEM fCRACS)

LIMITING CONDITION POR OPERATION 3.7.7.2 Two Control Room Air Conditioning System (CRACS) 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 CRACS train inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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

{

With one CRACS train inoperable, restore the inoperable system to a.

OPERABLE status within 30 days or immediately place the OPERABLE CRACS train in operation or insediately suspend movement of irradiated fuel assemblies and nevement of loads over irradiated fuel.

b.

With two CRACS trains inoperable, immediately suspend movement of irradiated fuel assemblies and movement of loads over irradiated fuel.

SURVEILLANCE REQUIREMENTS 4.7.7.2 At least once per le monthe verify that each CRACS train has the capability to remove the assumed heat loads.

l

The provisions of specification 3.0.4 are not applicable during the initial 30 days of implementation of control room cooling design changes.

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

111 1

N PLANT SYSTEMS BASES l

3/4 7.6.1 ULTIMATE HEAT SINK (RIVER)

This specification deleted.

l 3/4 7.6.2 ULTIMATE HEAT SINK (POND)

The limitations on the ultimate heat sink level and temperature ensure l

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.

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

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 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.

FARLEY-UNIT 2 B 3/4 7-4 AMENDMENT NO.111 I

PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROCM EMERGENCY VENTILATION SYSTEM (continued) i With one CRAC train inoperable, the inoperable train must be returned to OPERABLE status within 30 days. This Allowed Outa;e T;me is based on the low probability of complete loss of control room ecoling 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 mitigate the effects of componar.: f ailures, and the ti. e available to respond as loss of control room cooling does not have an immediate, irreversible impact.

While in MODES S and 6 during movement of irradiated fuel assemblies or movement of loads over irradiated fuel, if bcth trains of CRAC cannot be 1

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 habitab'e for operations personnel during and following all credible accident conditions.

3 /4.7. B ECCS PUMP ROOM EXMAUST AIR FILTRATION SYSTEM (PENETRATION ROOM AIR FILTRATION SYSTEM)

The OPERABILITY of the penetration room air filtration system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment. The operction of this system and the resultant ef fect on offsite dosage calculations was assumed in the accident analyses.

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

FARLEY-UNIT 2 B 3/4 7-4a AMENDMENT NO.111 l

>

ML20112C071

Text

Attachment:

Attachment:

Navigation menu

Search