Text

Amends 150,146 & 121 to Licenses DPR-33,DPR-52 & DPR-68, Respectively.Amends Modify Tech Spec Surveillance Requirements to Replace Not to Exceed W/At Least Once Every
	ML20150C544
Person / Time
Site:	Browns Ferry
Issue date:	07/05/1988
From:	Black S; NRC OFFICE OF SPECIAL PROJECTS
To:	;
Shared Package
ML20150C548	List: ML20150C544; ML20150C557;
References
	TAC-00037, TAC-00038, TAC-00039, TAC-37, TAC-38, TAC-39, NUDOCS 8807120528
	Download: ML20150C544 (33)
	v • d • e

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[

UNITED STATES o,,

E NUCLEAR REGULATORY COMMISSION o

E WASHINGTON, D. C. 20666 L

tg.....,o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENOMENT TO FACILITY OPERATIN'i LICENSE

)

Amendinent No.150 License No. OPR-33 1.

The Nuclear Regulatory Comission (the Comission) has found that A.

The application for amendment by Tennessee Valley Authority (the licensee) dated February 24, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the 8

provisions of the Act, and the rules and regulations of the Comission; C.

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

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

8807120520 000705 DR ADOCK 0500 9

I l.

l 2.

Accordingly, the license is amended by changes to tne Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-33 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.150, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION f

d.

I Suzann sistant Director for Projects l

TVA Projects Division Office of Special Projects I

Attachment:

Changes to the Technical i

Specifications I

Date of Issuance: July 5, 1988 l

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ATTACHMENT TO LICENSE AMEN 0 MENT N0.150 FACILITY OPERATING LICENSE NO. OPR-33 DOCKET NO. 50-259 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified. by the captioned amendment number and contain marginal lines indicating the area of change.

Overleaf pages* are provided to maintain document completeness.

REMOVE INSERT 3.7/4.7-19 3.7/4.7-19 3.7/4.7-20 3.7/4.7-20 3.7/4.7-21 3.7/4.7-21 3.7-4.7-22 3.7/4.7-22*

3.9/4.9-3 3.9/4.9-3*

3.9/4.9-4 3.9/4.9-4 3.11/4.11-3 3.11/4.11-3 3.11/4.11-4 3.11/4.11-4*

I

l L.2/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emeraency Ventilation 4.7.E Control Room Emeraency Ventilati2D

1. Except as specified in

1. At least once every 18 months, l Specification 3.7.E.3 below, the pressura drop across the both control room emergency combined HEPA filters and pressurization systems charcoal adsorber banks shall shall be OPERABLE at all be demonstrated to be les's than times when any reactor 6 inches of water at syst'em

. vessel contains irradiated design flow rate (i 10%).-

fuel.

2. a. The results of the in-place

2. a. The tests and sample cold DOP and halogenated analysis of Specification hydrocarbon tests at design 3.7.E.2 shall be performed flows on HEPA filters and at least once per operating charcoal adsorber banks cycle or once every shall show 199% DOP removal 18 months, whienever occurs and 199% halogenated first for standby service hydrocarbon removal when or after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of-tested in accordance with system ope. ration and i

ANSI N510-1975.

following significant.

painting, fire, or chemical' release in any ventilation :

zone communicating with the' system.

b. The results of laboratory

b. Cold DOP testing shall be carbon sample analysis shall performed after each show 190% radioactive methyl complete or partiali iodide removal at a velocity replacement of the HEPA when tested in accordance filter bank or after any with ASTM D3803 structural maintenance on (130'C, 95% R.H.).

the system housing.

c. System flow rate shall be

c. Halogenated hydrocarbon shown to be within i10%

testing shall be performed design flow when tested in after each complete or accordance with ANSI partial replacement of the N510-1975.

charcoal adsorber bank or after any structural maintenance on the system housing.

d. Each circuit shall be operated at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months every month.

BFN 3.7/4.7-19 Unit 1 Amendment No. M3150

3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emergency 4.7.E.

Control Room Emergency Ventilation Ventilation i

3. From and after the date that

3. At least once every 18 months, l

one of the control room automatic initiation of the emergency pressurization control room emergency systems is made or found to-pressurization system'shall be be INOPERABLE for any reason, demonstrated.

reactor operation or refueling

)

operations is permissible only during the succeeding 7 days unless such circuit is sooner made OPERABLE.

4. If thece conditions cannot be

4. During the simulated automatic met, reactor shutdown shall be actuation test of this system initiated and all reactors (see Table 4.2.G), it shall be shall be in Cold Shutdown verified t!.at the following within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for reactor dampers operate as indicated:

operations and refueling operations shall be terminated-Close FCO-150 B, D, E, and F within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Open:

FCO-151, FCO-152 I

i Amendment No. 150 BFN 3.7/4.7-20 Unit 1

e e

3.7/4.7 ColfriffGENT SYSTEMS SURVEILLANCE REQUIREMENTS LIMITING CONDITIONS FOR OPERATION 4.7.F.

Primary Containment Purae 3.7.F. Primary Containment Purae System System

1. The primary containment shall

1. At least once every 18 months, l

be normally vented and purged the pressure drop across the combined HEPA filters and through the primary containment charcoal adsorber banks shall purge system. The standby gas be demonstrated to be less than treatment system may be used 8.5 inches of water at system when primary containment purge design flow rate (i 10%).

system is INOPERABLE.

2. a. The results of the in-place

2. a. The tests and sample cold DOP and halogenated analysis of Specification 3.7.F.2 shall be performed hydrocarbon teste at design flows on HEPA filters and at least once per operating charcoal adsorber banks shall cycle or once every show 199% DOP removal and 18 months, whichever occurs first or after-720 hours 199% halogenated hydrocarbon removal when tested in of system operation and following significant accordance with painting, fire, or chemical ANSI N510-1975.

release in any ventilation zone communicating with the systen.

b. The results of laboratory

b. Cold DOP testing shall be carbon sample analysis performed after each shall show 185% radioactive complete or partial methyl iodide removal when replacement of the HEPA tested in accordance with filter bank or af ter any structural maintenance on ASTM D3803.

(130*C 95% R.H.).

the system housing.

c. System flow rate shall be

c. Halogenated hydrocarbon shown to be within i10% of testing shall be performed design flow when tested in after each complete or accordance with ANSI N510-partial replacement of the charcoal adsorber bank or 1975.

after any structural maintenance on the system housins.

BFN 3.7/4.7-21 Amendment No. 143 150 Unit 1

l 3.7/4.7 CONTAINMENT SYSTEMg LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.G.

Containment Atmosphere 4.7.G.

Conf.ainment Atmosphere Dilution System (CAD)

Qilation System (CAD) 1.

The Containment Atmosphere 1.

System Operability Dilution (CAD) System shall be OPERABLE with:

a.

Two independent a.

At least once systems capable of per month cycle supplying nitrogen each solenoid to the drywell and operated air /

torus.

nitrogen valve through at least one complete cycle of full travel and verify that each manual valve in the flow path is open.

b.

A minimum supply of b.

Verify that the CAD 2,500 gallons of System contains a

-liquid nitrogen per minimum supply of system.

2,500 gallons of liquid nitrogen twice per week.

2.

The containment Atmosphere 2.

When FCV 84-8B is Dilution (CAD) System shall INOPERABLE, each be OPERABLE whenever the solenoid operated reactor mode switch is in air / nitrogen valve the "RUN" position.

of System B shall be cycled through at least one complete cycle of full travel and each manual valve in the flow path of System B shall be verified open at least once per week.

3.

If one system is INOPERABLE, the reactor may remain in operation for a period of 30 days provided all active components in the other system are OPERABLE.

BrW 3.7/4.7-22 Unit 1

i

,1 3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Auxiliary Electrical Equipment, 4.9.A.

Auxiliary Electrical System 3.9.A.1.c.

(Cont'd) 4.9.A.1.b.2.(Cont'd)

NOTE FOR (3) AND (4):

permanently connected loads, the auto-With no cooling tower pumps connected emergency or fans running, a cooling loads are energized tower transformer may be through load substituted for a common sequencing, and station-service transformer.

the diesel operates for greater than or equal to five minutes while its generator is loaded with the emergency loads.

c.

Once a month the quantity of diesel fuel available shall be logged.

d.

Each diesel generator shall be given an annual inspection in accordance with.

instructions based on the manufacturer's recommendations.

I e.

Once a month a sample of diesel fuel shall be checked for quality.

The quality shall be within acceptable limits specified in Table 1 of the latest revision to ASTM D975 and logged.

BFN 3.9/4.9-3 Unit 1

3.9/4.9 AUIILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Auxiliary Electrical Equipment 4.9.A.

Auxiliary Electrical System l'

2. The reactor shall not be 2.

DC Power System - Unit started up (made critical)

Batteries (250-V), Diesel-from the hot standby condition Generator Batteries (125-V) unless all of the following and Shutdown Board Batteries conditions are satisfied:

(250-V) a.

At least one offsite power a.

Every week the specific source is available as gravity, voltage and specified in 3.9.A.1.c.

temperature of the pilob cell and overall battery voltage snall be measured and logged.

b.

Three units 1 and 2 diesel b.

Every three months the generators shall be measurement shall be made OPERABLE.

of voltage of each cell to nearest 0.1 volt, specific gravity of each cell, and temperature of

)

every fifth cell.

Theus measurements shall be logged.

c.

An additional source of c.

At least once every 24 power consisting of one months, a battery rated of the following:

discharge (capacity) test shall be performed (1) A second offsite and the voltage, time, power source available and output current as specified in measurements shall 3.9.A.1.c.

be logged.

(2) A fourth OPERABLE units 1 and 2 diesel generator.

d.

Requirements 3.9.A.3 through 3.9.A.6 are met.

i BFW 3.9/4.9-4 Amendmene. No. 150 Unit 1 I

I

y j

3.11/4.11 FIRE PROTECTION SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11.A.

High Pressure Fire Protection 4.11.A.

High Pressure Fire System Protection System area where protection is lost is checked hourly.

3.

If only one high

3. Raw Service Water pressure fire pump is System Testina OPERABLE, the reactors may remain Item Frequency in operation for a period not to exceed Simulated once/ year 7 days, provided the automatic requirements of and manual Specification actuation 3.11.A.1.b above of raw service are met.

water pumps and operation l

of tank level switches.

4.

If Specification

4. The high pressure 3.11.A.3 cannot be fire protection met', the reactors system pressure shall be placed in shall be logged

'the Cold Shutdown

daily, condition in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I S.

Removal of any

5. Principal header component in the High and component Pressure Fire System isolation valves fron service for any shall be checked reason other than open at least once testing or emergency every 3 months.

operations shall require Plant l

Manager approval.

6.

The Raw Service Water storage tank level shall be maintained above level 723'7" by the raw service water pumps.

BF4 3.11/4.11-3 Amendment No. 135 150 W

1

3.11/4.11 FIRE PROTECTION SYSTEkW LIMITING CONDITIONS'FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11.A.

Hith Pressure Fire Protschion 4.11.A.

High Pressure Fire System Protection System 7.

If Specification 3.11.A.6 cannot be met a fire pump shall be started and run continuously until the raw service water pumps can maintain a raw service water storage tank level above 723'7".

8.

The fire protection

. water distribution system shall have a minimum capacity of 2664 spa.t 250' head.

9.

The fire protection system shall be capable of supplying the individual loads listed in Table 3.11.A.

B.

C92 Fire Protection System B.

G92 Fire Protection System FireProtectkon 1.

The CO2 Fire 1.

CO2 Protection System Testing:

shall be OPERABLE:

Item Frequency l

a.

With a minimum a.

Simulated Once/ year of 8-1/2 tons automatic (0.5 Tank) CO2 and manuel l

l in storage units actuation 1 and 2.

b.

With a minimum b.

Storate checked of 3 tons (0.5 tank daily Tank) CO2 Pressure i

storage unit 3.

and level l

I LJW 3.11/4.11-4 Unit 1

l a assey'o, UNITED STATES 8

NUCLEAR REGULATORY COMMISSICN o

WASHINGTON, D C. 20566 n

j l

,/

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.146 License No. DPR-52 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated February 24, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the aoplication, the-provisions of the Act, and the rules and regulatin a of the Comission; C.

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

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety 6f the public; and E.

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

=. -.

l 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. DPR-52 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.146, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license acnendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION i SuzannkBlack,AssistantDirector for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: July 5, 1988 9

I

,_-__.___.-,_,_._._..y_,f,___,_,.

,_,,,_m.

n ATTACHMENT TO LICENSE AMENOMENT NO.

146

~

FACILITY OPERATING LICENSE N0. OPR-52 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications by remo,ing the pages identified below and inserting the enclosed pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided +.o maintain document completeness.

~

REMOVE 1NSERT 3.7/4.7-19 3.7/4.7-19 3.7/4.7-20 3.7/4.7-20 3.7/4.7-21 3.7/4.7-21 3.7-4.7-22 3.7/4.7-22*

j 3.9/4.9-3 3.9/4.9-3*

3.9/4.9-4 3.9/4.9-4 3.11/4.11-3 3.11/4.11-3 3.11/4.11-4 3.11/4.11-4*

3.7/4.7 C01rrAIlOMNT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emersency Ventilation 4.7.E. Control Room Emeraency Ventilation

1. Except as specified in

1. At least once every 18 months, l.

Specification 3.7.E.3 belov, the pressure drop across the both control room emergency combined HEPA filters and pressurization systems charcoal adsorber banks shall shall be OPERABLE at all be demonstrated to be less than times when any reactor 6 inches of water at system vessel contains irradiated design flow rate (

10%).

fuel.

2. a. The results of the in-place

2. a. The tests and sample cold DOP and halogenated anklysis~of Specification hydrocarbon tests at design 3.7.E.2 shall be performed flows on HEPA filters and at least once per operating charcoal adsorber banks cycle or once everv shall show 199% DOP removal 18 months, whichever occurs and 199% halogenated first for standby service hydrocarbon removal when or after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of tested in accordance with system operation and ANSI H510-1975.

following significant painting, fire, or chemical release in any ventilation zone communicating with the system.

b. The results of laboratory

b. Cold DOP testing shall be carbon sample analysis shall performed after each show 190% radioactive methyl complete or partial iodide removal at a velocity replacement of the HEPA when tested in accordance filter bank or after any with ASTM D3803 structural maintenance on (130*C, 95% R.H.),

the system housing.

c. System flow rate shall be

c. Halogenated hydrocarbon shown to be within i10%

testing shall be performed design flow when tested in after each complete or accordance with ANSI partial replacement of the i

N510-19'i5.

charcoal adsorber bank or after any structural l-maintenance on the system

housing,

d. Each circuit shall be operated at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months every month.

BFN 3.7/4.7-19 Amendment No. 139 146 Unit 2 2

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3. 7 /_4. 7 CONTAli

.? SYST5tE LIMITING COWDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emertency 4.7.E.

Control Room Rmergency Ventilation Ventilation

3. From and after the date that

3. At least once overy 18 months, l

one of the control room automatic initiation of the emergency pressurization control room emergency systems is made or found to pressurization system shall be be INOPERABLE for any reason, demonstrated.

reactor operation or refueling operations is permissible only during the succeeding 7 days' unless such circuit is sooner made OPERABLE.

4. If these conditions cannot be

4. During the simulated automatic met, reactor shutdown shall be actuation test of this system initiated and all reactors (see Table 4.2.G), it shall be shaL1 be in Cold Shutdown verified that the following within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for reector dampers operate as indicated, operations and refueling operations shall be terminated Close: FCo-150 B, D, E, and F within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Open:

FCo-151 l

FCO-152 1

i Amendment No. 146 Ut t2

I 3.7/4.7 CONTiflOElff SYSTEMS LIMITING CONDITIONS POR OPERATION SURVEILLANCE REQUIREMENT 6 3.7.F. Primary Containment Purae 4.7.F.

- Primary Containment Purae System System

1. The primary containment shall

1. At least once every 18 months, l

be normally vented and purged the pressure drop across the through the primary containment combined HEPA filters and purge system. The standby gas charcoal adsorber banks shall treatment system may be used be demonstrated to be less than when primary containment purse 8.5 inches of water at system system is IN0PERABLE.

design flow rate (i 10%).

2. a. The results of the in-place

2. a. The tests and sample cold DOP and halogenated analysis of Specification hydricarbon tests at design 3.7.F.2 shall be performed flows on HEPA filters and at least once per operating charcoal adsorber banks shall cycle or once every show 199% DOP removal and 18 months, whichever occurs 199% halogenated hydrocarbon first or after 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months removal when tested in of system operation and accordance with following significant ANSI N510-1975.

painting, fire, or chemical release in any ventilation zone communicating with the system.

b. The results of laboratory

b. Cold DOP testing sht11 be carbon sample analysis performed after each shall show 185% radioactive complete or partial methyl iodide removal when replacement of the KEPA tested in accordance with filter bank or af ter any ASTM D3803.

structural maintenance on I

(130*C 95% R.H.).

the system housing.

I

c. System flow rate shall be

c. Halogenated hydrocarbon shown to be within 10% of testing shall be performed design flow when tested in after each complete or accordance with ANSI N510-partial repit.coment of the 1975.

charcoal adsorber bank or after any structural maintenance on the system housing.

i 1

Amendment No. 139 146 BFN 3.7/4.7-21 Unit 2

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+t--*w---%we-w,weg.-g-

U 3.//4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.C. Containment Atmosphere 4.7.G.

Containment Atmosphere Dilution System (CAD)

Dilution System (CAD) 1.

The Containment Atmosphere 1.

System Operability Dilution (CAD) System shall be OPERABLE with:

a. Two independent a.

At least once systems capable of per month cycle each solenoid supplying nitrogen to the drywell and operated air /

nitrogen valve torus.

through at least one complete cycle of full travel and verify that each manual valve in the flow path is open,

b. A minimum supply of b.

Verify that the CAD 2,500 gallons of System contains a liquid nitrogen per minimum supply of system.

2;500 gallons of liquid nitrogen twice per week.

2.

The Containment Atmosphere Dilution (CAD) System shall be OPERABLE whenever the reactor mode switch is in I

the "RUN" position.

3.

If one system is INOPERABLE, the reactor may censin in operation for a period of 30 days provided all active components in the other system are OPERABLE.

1 l

BFN 3.7/4.7-22 Unit 2

3.9/4.9 AUKILIARY ELECTRICAL SYSTEN LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Auxiliary Electrical Equipment 4.9.A.

Auxiliary Electrical System 3.9.A.1.c.

(Cont'd)

4. 9. A.1.b. 2. (Cont' d)

NOTE FOR (3) AND (4):

permanently connected loads, the auto-With no cooling tower pumps co.nected emergency or fans running, a cooling loads are energized tower transformer may be through load substituted for a common sequencing, and station-service transformer.

the diesel operates for greater than or equal to five minutes while its generator is loaded with the emergency loads.

c.

Once a month the quantity of diesel fuel available shall be logged, d.

Each diesel generator shall be given an annual inspection in accordance with instructions baeed on the manufacturer's recommendations.

I e.

Once a mon.th a sample of diesel fuel shall te checked for quality.

The quality shall be within kcceptable limits specified in Table 1 of the latest revision to ASTM D975 and logged.

3.9/4.9-3 gF{

U 3.9/4.9 AUXILIARY ELECTRICAL SYSTEM j

l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Auxiliary Electrical Eauipment 4.9.A.

Auxiliary Electrical System

'l

2. The reactor shall not be 2.

DC Power System - Unit j

j started up (made critical)

Batteries (250-V), Diesel-from the hot standby condition Generator Batteries (125-V) unless all of the following and shutdown Board Batteries conditions are satisfied:

(250-V) a.

At least one offsite power a.

Every week the specific source is available' as gravity, voltage and specified in 3.9.A.1.c.

temperature of the pilot cell and over'll battery a

voltage shall be measured and logged.

b.

Three units 1 and 2 diesel b.

Every three months the generators shall be measurement shall be made OPERABLE.

of voltage of each cell to nearest 0.1 volt, specific gravity of each e

cell, and temperature of every fifth cell.

These measurements shall be logged.

c.

An additional source of c.

At least once every 24 pcVer consisting of one months, a battery rated of the following:

discharge.(capacity) test shall be performed (1) A second offsite and the voltage, time, power source available and output current as specified in measurements shall 3.9.A.1.c.

be logged.

(2)'A fourth OPERABLE units 1 and 2 diesel generator.

i d.

Requirements 3.9.A.3 through 3.9.A.6 are met.

BFN 3.9/4.9-4 Amenoment No. 146 Unit 2

r-u 3.11/4.11 FIRE PROTECTIQW SYSTEMS LIMITING CONDITIONS FOR_0PERATION SURVEILLANCE REQUIREMENTS 3.11.A.

High Pressure Fire Protection 4.11.A.

High Pressure Fire Systes Protection System area where protection is lost is checked hourly.

3.

If only one high

3. Raw Service Water pressure fire puwp is System Testina f

OPERABLE, the reactors may remain Iten Frequency in operation for a period not to exceed Simulated Once/ year 7 days, provided the automatic requirements of-and manual Specification actuation 3.11.A.1.b above of raw service 1

are met.

water pumps and operation of tank level switches.

4.

If.. Specification

4. The high pressure 3.11.A.3 cannot be fire protection met, the reactors system pressure shall be placed in shall be logged the Cold shutdown

daily, condition in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5.

Removal of any

5. Principal header i component in the High and component Pressure Fire System isolation valves j

from service for any shall be checked reason other than open et least '

l testing or emergency every 3 month I

j operations shall require Plant

I Manager approval.

6.

The Raw Service Water storage tank level shall be maintained above level 723'7" by the raw service water pumps.

BFW 3.11/4.11-3 Amendment No. J34 146 Unit 2

a g

3.11/4.11 FIRE PROTECTION SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

~

3.11.A.

High Pressure Fire Protection 4.11.A.

High Pressura Fire System Protection System 7.

_If Specification 3.11.A.6 cannot be met a fire pump shall be started and run continuously until the raw service water pumps can maintain a raw service water storage tank let'al above 723'7".

8.

The fire protection water distribution system shall have a minimum capacity of 2664 gym et 250' head.

9.

The fire pectaction system shall be j

capable of supplying the indiviesa; icads listed in t able i

3.11.A.

l 4

i B.

292 Fire Protection System B.

992 Fire' Protection System 1.

The CO2 Fire 1.

CO2 Fire Protection Protection System Testing I

shall be OPERABLE:

Item Frequency a.

With a minimum a.

Simulated once/ year of 8-1/2 tons automatic and manual (0.5 Tank) CO2 in storage units actuation i

l 1 and 2.

i b.

With a minimum b.

Storage Checked of 3 tons (0.5 tank daily Tank) CO2 pressure storage unit 3.

and level i

l I

l i

BFN 3.11/4.11-4 Unit 2

_,--__n.,-.

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

/

UNITED STATES o,,

8 NUCLEAR REGULATORY COMMISSION o

{

,it WASHINGTON, D. C. 20585

\\...../

ENNESSEEVALLEYAUTHORITY DOCKET N0. 50-296 BROWNS FERRY NUCLEAR PLANT UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.121 License No. DPR-68 4

1.

The Nuclear Regulatory Consission (the coamission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated February 24, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Consission's rules and 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; l

C.

There is reasonable assurance (1).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 Co.uission's regulations; D.

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

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements h6ve been satisfied.

4 l

j

., ~ _. - - --

1 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. DPR-68 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.146, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ACb

( 2-A Sulann

, Assistant Director for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to tae Technical Specifications Dats of Issuance:

July 5, 1988 3

- - ~

ATTACHMENT TO LICENSE AMEN 0 MENT NO.121 FACILITY OPERATING LICENSE NO. OPR-68 DOCKET NO. 50-296 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages are idehtified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are prov'aed to maintain document completeness.

REMOVE INSERT 3.7/4.7-19 3.7/4.7-19 3.7/4.7-20 3.7/4.7-20 3.7/4.7-21 3.7/4.7-21 3.7/4.7-22, 3.7/4.7-22*

3.9/4.9-3 3.9/4.9-3*

3.9/4.9-4 3.9/4.9-4 3.11/4.11-3 3.11/4.11-3 3.11/4.11-4 3.11/4.11-4*

I p

.--,.--.,..w.

I

?

3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control' Room Emermancy Ventilation 4.7.E Control Room Emermancy Ventilation

1. Except as specified in

1. At least once every 18 months, l Specification 3.7.E.3 below, the pressure drop across the both control room emergency combined HEPA filters and pressurization systems charcoal adsorber banks shall shall be OPERABLE at all be demonstrated to be less than times when any reactor 6 inches of water at system vessel'contains irradiated design flow rate (i 10%).

fuel.

2. a. The results of the inplace

2. a. The tests and sample cold DOP and halogenated analysis of Specification hydrocarbon tests at design 3.7.E.2 shall be performed flows on HEPA filters and at least once per operating charcoal adsorber banks cycle or once every shall show 199% DOP removal 18 months, whichever occurs and 199% halogenated first for standby service hydrocarbon removal when or after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of tested in accordance with system operation and ANSI N510-1975.

following significant painting, fire, or chemical

' release in any ventilation zone cosununicating with the system.

b. The results of laboratory

b. Cold DOP testing shall be carbon sample analysis shall performed;after each show 190% radioactive methyl complete or partials iodide removal at a vr.locity replacement of the HEPA when tested in accordance filter bank or after any with ASTM D3803 structural maintenance on (130*C, 95% R.H.).

the system housing.

c. System flow rate shall be

c. Halogenated hydrocarbon shown to be within i10%

testing shall be performed design flow when tested in after each complete or accordance with ANSI partial replacement of the charcoal adsorber bank or N510-1975.

after any structural maintenance on the system housing.

d. Each circuit shall be operated at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months j

every month.

I BFN Unit 3 3.7/4.7-19 Amendment No. Z%4 121

)

1 j

~.

I 3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control. Room Emergency 4.7.E.

Control Room Emergency Ventilation Ventilation

3. From and after the date that

3. At least once every 18 months, one of the control room automatic initiation of the emergency pressurization control room emergency systems is made or found to pressurization system shall be i

be INOPERABLE for any reason, demonstrated.

reactor operation or refueling j

operations is permissible only during the succeeding 7 days unless.such circuit is sooner made OPERABLE.

4. If these conditions cannot be

4. During the simulated automatic met, reactor shutdown sh'all be actuation test of this system initiated and all reactors (see Table 4.2.G), it shall be shall be in Cold Shutdown verified that the following within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for reactor dampers operate as indicated:

operations and refueling operations shall be terminated Close: FCO-150 B D, E, and F within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Opent FCo-151, FCo-152 l

BrW Unit 3 3.7/4.7-20 Amendment No. 121 i

U 3.7/4.7 CONTAfleENT SYSTDL%

LIMITING CONDITIONS FOR OPERATION SUPVEILLANCE REQUIREMENTS 3.7.F. Primary Containment Purze 4.7.T.

Primary Containment Purgs System System

1. The primary containment shall

1. At least once every 18 months l be normally vented and purged the pressure drop across the through the primary containment combined HIPA filters and purge system. The standby gas charcoal adsorber banks shall treatment system may be used be demonstrated to be less than when primary containment purge 8.5 inches of water at system system is INOPERABLE.

design flow rate (i 10%).

2. a. The results of the in-place 2

a. The tests and sample cold DOP and halogenated analysis of Specification hydrocarbon tests at design 3.7.T.2 shall be performed flows on HEPA filters and at least once per operating charcoal adsorber banks shall cycle or once every show 199% DOP removal and 18 months, whichever occurs 199% halogenated hydrocarbon first or after 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months removal when tested in of system operation and accordance with following significant ANSI N510-1975.

painting, fire, or chemical release in any ventilation zone communicating with the system.

b. The resulta of laboratory b'.

Cold DOP testing shall be carbon sample sahlysis performed after each shall show 185% radictetive complete or partial methyl iodide removal whe0 replacement of the HEPA l

tested in accordance with filter bank or af ter any i

ASTM D3803.

structural maintenance on (130'C 95% R.H.).

the system housing.

e. System flow rate shall be

c. Halogenated hydrocarbon shown to be within 110% of testing shall be performed design flow when tested in after each complete or accordance with ARSI R510-partial replacement of the j

1975.

charcoal adsorber bank or after any structural j

maintenance on the system housing.

l BFN Unit 3 3.7/4.7-21 Amendment No. Il4 121

3.7/4.7 CO M NMgMT.. SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.G.

Containment Atmosphere 4.7.G.

Containment Atmosphere Dilution System (CAD)

Dilution System (CAD) 1.

The Containment Atmosphere 1.

System Ooscability Dil'ution (CAD) System shall be OPERABLE with:

a.

Two independent a.

At least once per systems capable of month cycle each supplying nitrogen solenoid-operated to the drywell and air / nitrogen valve torus.

through at least one complete cycle of full tesvol and verify that each manual valve in the flow path is open.

b.

A minimum supply of b.

Verify that the CAD 2,500 gallons of System contains a liquid nitrogen per minimum supply of system.

2,500 gallons of liquid nitrogen twice per week.

2.

The Containment Atmosphere Dilu' tion (CAD) System shall be OPERABLE whenever the reactor mode switch is'in the "RUM" position.

3.

If one system is INOPERABLE, the reactor may remain in operation for a period of 30 days provided all active components in the other system are OPERABLE.

4.

If Specifications 3.7.G.1 and 3.7.G.2, or 3.7.G.3 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5.

primary containment pressure shall be limited to c maximum of 30 pois during repressurization following a loss of coolant accident.

3.7/4.7-22 gr{ 3 t

M /4.9 AVEIf.IARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Auxillary Electrical 4.9.A.

Auxiliary Electrieel toutument System

3. 9. A.1. c. ( 3)

(Cont'd) 4.9.A.1.b.(3)

(Cont'd) t station-service connected emergency transformer A or loads are energized cooling tower through load transformer 1, and sequencing, and the the Trinity line diesel operates for must. supply unit 3 greater than or equal through common station-to five minutes while service transformer B or its generator is loaded cooling tower transformer 2.

with the emergency loads.

c.

Once a month the quantity of diesel fuel available shall be

'ogged.

d.

Each diesel generator shall be given an annual inspection in accordance with instructions based on

' the manuf acturer's recommendations.

e.

Once a month a sample of diesel fuel shall be checked for quality.

The quality shall be within acceptable limits specified in Table 1 of the latest revision to ASTM D975 and logged.

hkft3 3.9/4.9-3 l

1 3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Auxiliary Electrical Eaulement 4.9.A.

Auxiliary Electrical System 2.

The reactor shall not be 2.

DC Power System - Unit started up (made critical)

Batteries (250-V),

from the Hot Standby condition Diesel-Generator unless all of the following Batteries (125-V)and conditions are satisfied Shutdown Board Batteries (250-V) a.

At least one offsite power a.

Every week the source is available as specific gravity,

~

specified in 3.9.A.1.c.

voltage, and temperature of the pilot cell, and overall battery voltage shall be measured and logged.

b.

Three units 3 diesel b.

Every three months generators shall be the measurements OPERABLE.

shall be made of voltage of each cell to nearest 0.1 volt, specific gravity of each cell, and temperature of every fifth cell.

These measurements shall be lossed.<

c.

An additional source of e.

At least once every 24 power consisting cf one months, a bettery rated of the following:

discharge (capacity) test shall be performed (1) A secor.d offsite and the voltage, time, I

power source availabis and output current as specified in measurements shall 3.9.A.1.c.

be logged.

(2) A fourth unit 3 diesel generator OPERABLE.

d.

Requirements 3.9.A.3 through 3.9.A.6 are met.

i BFW Unit 3 3.9/4.9-4 Amendment No. 121.

t 1

1111/4.11 FIRE PROTECTION SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11.A.

High Pressure Fire Protection 4.11.A.

High Pressure Fire System Protection Systgg 3.11.A.2.

(Cont'd) area where protection le lost is checked hourly.

3.

If only one high

3. Raw Service Water pressure fire pump is Systes Testina OPERABLE, the reactors may remain liga Frequency 4

in operation for a j

period not to exceed Simulated Onca/ year 7 days, provided the automatic i

requirements of and manual Specification actuation 3.11.A.1.b above of raw service i

are met.

water pumps and operation of tank level switches.

j 4.

If Specification

4. The high pressure q

i 3.11.A.3 cannot be fire protection met, the reactors system pressure shall be placed in shall be logged the Cold Shutdown daily.

/

condition in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5.

Removal of any

5. Principal header component in the High and component Pressure Fire System isolation valves from service for any shall be checked reason other than open at least once testing or emergency every 3 months.

operations shall require Plant Manager approval.

6.

The Raw Service Water storage tank level shall be maintained above level 723'7" by the raw serv.ca water pumps.

I BFW Unit 3 3.11/4.11-3 Amendment No. 109 121 I

i

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

O 3.11/4.11 FIRE PROTECTION SYSTun i

I,IMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11.A.

Hlah Pressure Fire Protection 4.11.A.

Hiah Pressure Fire 1y1135 Protection System 7.

If Specification 3.11.A.6 cannot be met, a fire pump shall

(

be started and run i

continuously until the raw service water l

pumps can maintain a raw service water storage tank level above 723'7".

3.

The fire protection water distribution system shall have a minimum capacity of 2.664 spa at 250' head.

9.

The fire protection system shall be l

capabis of supplying the individual loads listed in Table 3.11.A.

l E.

$22 Fire Protect 1 6 s_t3 B.

QQ2 Fire Pro 19thign System 1.

The CO2 Fire 1.

CO2 Fire Protection Protection System Testing:

shall be OPERABLg:

Iles Frequency a.

With a minimum a.

Simulated once/ year of 8-1/2 tons automatic (0.5 Tank) CO2 and manual in storage units actuation I and 2.

b.

With a minimum b.

Storage Checked of 3 tons (0.5 tank daily Tank) CO2 pressure storage unit 3.

and level 4

i I.

$$Yt3 3.11/4.11-4 i

l I

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

v t e Letter Sequence Other
TAC:00037, (Approved, Closed) TAC:00038, (Approved, Closed) TAC:00039, (Approved, Closed)
Initiation Request Acceptance... Administration Questions Answers Results Approval Other: ML18032A726, ML20150C544
MONTHYEAR1988-02-24 [Table View]

ML20150C544

Text

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