Text

Amends 151,147 & 122 to Licenses DPR-33,DPR-52 & DPR-68, Respectively.Amend Modifies Tech Specs by Changing Operability Requirements for Standby Gas Treatment Sys & Control Room Emergency Ventilation Sys
	ML20151K739
Person / Time
Site:	Browns Ferry
Issue date:	07/20/1988
From:	Black S; NRC OFFICE OF SPECIAL PROJECTS
To:	;
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ML20151K744	List: ML20151K739; ML20151K747;
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	NUDOCS 8808030269
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'o, UNITED ST ATES i'S j

NUCLEAR REGULATORY COMMISSION W ASMNOTON, D. C. 20555 July 20, 1988

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i TENf!ESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BR0n s FERRY NUCLEAR PLANT, UNIT 1 APENDMENT TO FACILITY OPERATING LICENSE Amendment No. 151 License No OPR-33 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated June 1, 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 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 saf ety 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 cocinon 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 c.atisfied.

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. Accordingly, the license is amended by changes to the Technical 2.

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 Scecificatinns The Technical Specifications contained in Appendices A and B, as revised through Amendment No.151, are hereby incorporated in the The licenste shall operate the facility in accordance with licensc.

the Technical Specifications.

This license amendment is ef fective as of its date of issuance and shall 3.

be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

-,' K G 4C Suzann lack, Assistant Director for Projects TVA Projects Divisior.

Office of Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: July 20, 1988

N 9

ATTACHF.ENT TO LICENSE AMENDMENT NO. 151 FACILITY OPEP.ATING LICEh'SE NO. OPR-33 00CKET N0. 50-259 Revise the Appendix A Technical Specifications by removing the pages identifico 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 3.7/4.7-13 3.7/4.7-13 3.7/4.7-14 3.7/4.7-14*

3.7/4.7-15 3.7/4.7-15 3.7/4.7-15a 3.7/4.7-15a 3.7/4.7-16 3.7/4.7-16*

3.7/4.7-19 3.7/4.7-19*

3.7/4.7-20 3.7/4.7-20 l

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t 3.7/t. 7 CONTAIN!ENT SYSTEfiS lit 4ITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B.

Standby Gas Treatment System 4.7.B. Standby Gas Treatment System

la. Except as specified in

1. At least once per year, l

Specification 3.7.B.3 below, the following conditions all three trains of the shall be demonstrated.

standby gas treatment system shall be OPERABLE at all a.

Pressure drop across times when secondary the combined REPA containment integrity is filters and charcoal adsorber banks is less

required, than 6 inches of water lb. With no fuel in any reactor at a flow of 9000 cfm vessel, only two (2) of the (i 10%).

three (3) standby gas treat-ment trains are required b.

The inlet heaters on to be OPERABLE at all times each circuit are when secondary containment tested in accordance integrity is required.

If with ANSI N510-1975, either of the two (2) standby and are capable of an gan treatment system trains output of at least become inoperable at any time 40 kW.

when operability is required, suspend handling of irradiated c.

Air distribution is fuel until two (?) trains of uniform within 20%

standby gas treatment are across HEPA filters OPERABLE.

and charcoal adsorbers.

With no fuel in any reactor vessel, Specification 3.7.B.1.b is applicable.

BFN 3.7/4.7-13 Amendment No. 151 Unit 1

I 3.7/4.7 CONTAIUMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B. Standby Gas Treatment System 4.7.B.

Standby Gas Treatment System 2

a. The results of the in-place

2. a. The tests and sample cold DOP and halogenated analysis of hydrocarbon tests at 1 10%

Specification 3.7.B.2 design flow on HEPA filters shall be performed at and charcoal adsorber banks least once per operating shall show 199% DOP removal cycle or once every and 199% halogenated 18 months whichever hydrocarbon removal when occurs first for standby tested in accordance with service or after every ANSI H510-1975.

720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation and 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 carbon sample analysis be performed after shall show 190% radioactive each complete or partial methyl iodide removal when replacement of the HEPA tested in accordance with filter bank or after any ASTM D3803 (130*C, structural maintenance 95% R.H.).

on the system housing.

c. System shall be shown to

c. Halogenated hydrocarbon operate within 110% design testing shall be

flow, performed after each complete or partial replacement of the charcoal adsorber bank or after any structural maintenance on the system housing.

BFN 3.7/4.7-14 Amendment No. 143 Unit 1

6 3.7 /4.7 C0'?TAIfi!!Ef!T SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B.

Standby Gas Treatment System 4.7.B. Standby Gas Treatment System 4.7.B.2 (Cont'd) d.

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

e.

Test sealing of gaskets for housing doors shall be performed utilizing chemical smoke generators during each test performed for compliance with Specification 4.7.B.2.a and Specification 3.7.B.2.a.

l*3.Fromandafterthedate 3.

a.

Once per operating cycle that one train of the automatic initiation of standby gas treatment each branch of the system is made or found standby gas treatment to be INOPERABLE for any system shall be reason, reactor operation demonstrated from each and fuel handling is unit's controls, permissible only during the succeeding 7 days unless b.

At least once per year such circuit is sooner made manual operability of OPERABLE, provided that the bypass valve for during such 7 days all active filter cooling shall be components of the other two demonstrated.

standby gas treatment trains shall be OPERABLE.

c.

When one train of the standby gas treatment system becomes INOPERABLE the other two trains shall be demonstrated to be OPERABLE within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and daily thereafter.

l

Not applicable with no fuel in any reactor vessel.

BFN 3.7/4.7-15 Amendment No. 151 Unit 1 i

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~. 7 < 4.7 COI TA!!EE!;T SYSTEMS I

LIMITI!iG C0!iDITI0liS FOR OPERATIOli SURVEILLAliCE REQUIREMEliTS 3.7.B. Standby Gas Treatment Syst_em 4.7.B.

Standby Gas Treatment System 3.7.B.3 (Cont'd) 4 If these conditions cannot be met, the reactor shall be placed in a condition for which the standby gas treatment system is not required.

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BFli 3.7/4.7-15a Amendment No. 151 Unit 1

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THIS PAGE I!rIENTIONALLY LEFT BLANK l

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3.7/4.7 CONTAINMENT SYSTEMS LIICTIIG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.C. Secondary Containment 4.7.C.

Secondary Containment

1. Secondary containment integrity

1. Secondary containment shall be maintained in the surveillance shall be reactor zone at all times performed as indicated except as specified in below:

3.7.C.2.

I

a. Secondary containment capability to maintain 1/4 inch of water vacuum under calm wind

(< 5 mph) conditions with a system leakage rate of not more than 12,000 cfm, shall be demonstrated at each refteling outage prior to refueling.

2. If reactor zone secondary

2. After a secondary containment integrity cannot containment violation is be maintained the following determined the standby gas conditions shall be met:

treatment system will be operated immediately after

a. The reactor shall be made the affected zones are suberitical and Specification isolated from the remali. der 3.3.A shall be met, of the secondary containment to confirm its

b. The reactor shall be cooled ability to maintain the down below 212'F and the remainder of the secondary containment at 1/4-inch reactor coolant system of water negative pressure

vented, under calm wind conditions.

c. Fuel movement shall not be permitted in the reactor zone.

d. Primary containment integrity maintained.

3. Secondary containment integrity shall be maintained in the refueling zone, except as specified in 3.7.C.4.

BFN 3.7/4.7-16 Unit 1

o 3.7'/4.7 CONTAINMENT SYSTEMS LI!:ITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emergency Ventilation 4.7.E Control Room Emerzency

~

Ventilation

1. Except as specified in

1. At least once per operating Specification 3.7.E.3 below, cycle, not to exceed both control room emergency 18 months, the pressure drop pressurization systems across the combined HEPA shall be OPERABLE at all filters and charcoal adsorber times when any reactor banks shall be demonstrated to vessel contains irradiated to be less than 6 inches of

fuel, water at system design flow rat (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.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 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 110%

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.

Amendment No. 143 BFN 3.7/4.7-19 Unit 1 l

I s

4 3.7/4.7 CONTAINMEirr SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room Emeraency 4.7.E.

Control Room Emergency Ventilation Ventilation

3. From and after the date that

3. At least once per operating one of the control room cycle not to exceed 18 months, emergency pressurization automatic initiation of the systems is made or found to control room emergency be IN0PERABLE for any reason, pressurization system shall be reactor operation or refueling demonstrated, 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 ar.d 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 .

Open: FCO-151 FCO-152 i

LCO not applicable with no fuel in any reactor vessel.

BFN 3.7.4.7-20 Amendment No. 151 Unit 1

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/pm atauq'o, UNITED STATES y (/ '

'n NUCLEAR REGULATORY COMMISSION

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M4. t WASHING TON, D. C. 20555 M

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMEh0 MENT TO FACILITY OPERATING LICENSE Amendment No. 147 License No. OPR-52 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated June 1, 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 conform'ity 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 amendment will not be inimical to the comon defense and security or to the health and safety of the public; and F.

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 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. OPR-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. 147, 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 impler.ented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

.(

u %R Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to the Tochnical Specifications Ddte of Issuance: July 20,1988 J

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,s ATTACHMENT TO LICENSE AMENDMENT N0.147 FtCILITY OPERATING LICENSE h0. OPR-52 DOCKET NO. 50-260 Pevise'the Apperdix A Technical Specifications by reniving 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 cf change. Overleaf pages* are provided to riaintain document completeness.

PEMOVE INS $RT

.3.7/4.7-13 3.7/4.7-13 3.7/4.7-14 3.7/4.7-14*

3.7/4.7-15 3.7/4.7-15 3.7/4.7-15a 3.7/4.7-15a 3.7/4.7-16 3.7/4.7-16*

3.7/4.7-19 3.7/4.7-19*

3.7/4.7-20 3.7/4.7-20 W

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3.7 /J. 7 C01 iAIN"EfiT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B.

Elandby Gas Treatment System 4.7.B. Standby Gas Treatment System l

1a. Except as specified in 1.

At least once per year, Specification 3.7.B.3 below, the following conditions all three trains of the shall be demonstrated.

s;endby gas treatment system shall be OPERABLE 'at all a.

Pressure drop across times when secondary the combined HEPA containment integrity is filters and charcoal

required, adsorber banks is less than 6 inches of water Ib. With no fuel in any reactor at a flow of 9000 cfm vessel, only two (2) of the (i 10%).

three (3) standby gas treat-ment trains are required b.

The inlet heaters on to be OPERABLE at all times each circuit are when secondary containment tested in accordance integrity is required.

If with ANSI N510-1975, either of the two (2) standby and are capable of an gas treatment system trains output of at least become inoperable at any time 40 kW.

when operability is required, suspend handling of irradiated c.

Air distribution is fuel until two (2) trains of uniform within 20%

standby gas treatment are across HEPA filters OPERABLE.

and charcoal adsorbers.

With no fuel in any reactor vessel, Specification 3.7.B.l.b is applicable.

Amendment No. 147 i 2 1

c 3.7/4.7 CONTAINMENT SYSTEMS LI!':!ING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS I

3.7.B. Standby Gas Treatment System 4.7.B. Standby Gas Treatment System

2. a. The results of the in-place

2. a.

The tests and sample cold DOP and halogenated analysis of hydrocarbon tests at 1 10%

Specification 3.7.B.2 design flow on HEPA filters shall be performed at and charcoal adsorber banks least once per shall show 199% DOP removal operating cycle or and 199% halogenated once every 18 months hydrocarbon removal when whichever occurs tested in accordance with first for standby ANSI N510-1975, service or after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation and 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 carbon sample analysis be performed after shall show'190% radioactive each' complete or partial methyl iodide removal when replacement of the HEPA tested in accordance with filter bank or after any ASTM D3803 (130'C, structural maintenance 95% R.H.).

on the system housing.

c. System shall be shown to c.

Halogenated hydrocarbon operate within 110% design testing shall be flow.

performed af ter each complete or partial replacement of the charcoal adsorber bank or after any structural meintenance on the system housing.

BFN 3.7/4.7 14 Amendment No. 143 Unit 2

w 1.7/4.7 - CONTAlfMEf;T SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B.

Standby Gas Treatment System 4.7.B. Standbv Gas Treatment System 4.7.B.2 (Cont'd) d.

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

e.

Test sealing of gaskets for housing doors shall be performed utilizing ebemical smoke generators during each test performed for compliance with Specification 4.7.B.2.a and Specification 3.7.B.2.a.

3.

From and after the date 3.

a.

Once per operating cycle that one train of the automatic initiation of standby gas treatment each branch of the system is made or found standby gas treatment to be INOPERABLE for any system shall be reason, reactor operation demonstrated from each and fuel'nandling is unit's controls.

permissible only during the succeeding 7 days unless b.

At least once per year such circuit is sooner made manuni operability of OPERABLE, provided that the bypass valve for during such 7 days all active filter cooling shall be components of the other two demonstrated.

standby gas treatment trains shall be OPERABLE.

c.

When one train of the standby gas treatment system becomes INOPERABLE the other two trains shall be demonstrated to be OPERABLE within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and daily thereafter.

Not applicable with no fuel in any reactor vessel.

BFN 3.7/4.7-15 Amendment No. 147 Unit 2

o -

0 3.7/4.7-Cof7AIIE!E SYSTE!!S i

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS f

3.7.B. Erindby Gas Treatm_ent Systen-4.7.B.

Standby Gas Treatment System 3.7.B.3 (Cont'd)

4. If these conditions cannot be met, the reactor shall be placed in a'conditior.-for which the standby gas treatment.

system is not required.

L t

BTN 3,7/4,7_35, Amendment No. 147 Unit 2

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THIS PAGE IITIENTIONALLY LFFT BLANK M

4 I

8 3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.C. Secondary Containment 4.7.C.

Secondary Containment

1. Secondary containment integrity 1.

Secondary containment shall be maintained in the surveillance shall be reactor zone at all times performed as indicated except as specified in below:

3.7.C.2.

a.

Secondary containment capability to maintain 1/4 inch of water vacuum under calm wind

(< 5 mph) conditions with a system leakage rate cf not more than 12,000 cfm, shall be demonstrated at each refueling outage prior to refueling.

2. If reactor zone secondary 2.

Af ter a secondary containment integrity cannot containment violation is be maintained the following determined the standby gas conditions shall be ret:

treatment system will be operated immediately after

a. The reactor shall be made the affected zones are suberitical and Specification isolated from the remainder 3.3.A shall be met, of the secondary containment to confirm its

b. The reactor shall be cooled ability to maintain the down below 212*F and the remainder of the secondary containment at 1/4-inch reactor coolant system

vented, of water negative pressure under calm wind conditions,

c. Fuel movement shall not be permitted in the reactor zone.

d. Primary containment integrity maintained.

3. Secondary containment integrity shall be maintained in the refueling zone, except as specified in 3.7.C.4.

i BTN 3.7/4.7-16 l

Unit 2

. fj '

3.7/4.7 COR'[AINMEfn SYSTEMS e,'

LI!GTINO CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS e

3.7.E. Control Room Emergency Ventilation 4.7.E Control Room Emergency Ventilation P

1. Except as specified in

1. At least once per operating Specification 3.7.E.3 below, cycle, not to exceed both control room emergency 18 months, the pressure drop pressurization systems across the combined HEPA shall be OPERABLE at all filters and charcoal adsorber times when any reactor banks shall be demonstrated to vessel contains irradiated to be less than 6 inches of

fuel, water at system 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.E.2 shall be perforced flows on REPA 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 communicating with tha system.

b. The results of laboratory

b. Cold DOP testint shall be carbon asmple analysis shall performed after each complete or partial show 190% radioactive methyl lodidt removal at a velocity replacement of the HEPA when tested in accordance filter bank or after any with ASTM D3803 etructural maintenance on (330'C, 95% R.H.).

the system housing.

c. System flow rate shall be

c. Halogenated hydrocarbon shown to be within 110%

testing shall be performed design flow when tested in after each complete or accordaace with ANSI partial repiccoment 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.

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

o., -

ip C

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

Ortliol_ Room Emergency Ventilation (f.y'14tian

3. From and after the date that

3. At leae ac p'r operating one of the control room cycle not xceed 18 months, emergency pressurization automatic ciation of the systems is made or found to control

..o emergency be INOPERABLE for any reason, pressur1Lation system shall be reactor operation or refueling demonstrated.

operations is Ostmissible 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 syatem initiated and all reactors (ren. 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 .

Open: FCO-151 FCO-152

LCO not applicable with no fuel in any reactor vessel.

tFN 3.7.4.7-20 Amendment No. 147 Unit 2

,,f A

p raag#

UNITED STATES g

</ j NUCLEAR REGULATORY COMMISSION y

c WASHINGTON. D. C. 20655 July 20, 1988 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMEfT TO 'xCILITY OPERATING LICENSE Amendment No.122 License No. DPR-68 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) Jated June 1, 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 provisions of the Act, and the rules and regulations of the Comission; l

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 amendment will not be inimical to the comon defense and security or to the health and safety of the public; and l

E.

The issuan:e of this amendment i'. ir accordance with 10 CFR Part 51

~

of the Comission's regulations and all applicable requirements ha"-

been satisfied.

i l

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l l-

l

?.,, 1 i

p

- 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in thc attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-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.122, are hereby incorporated in the license. The licensee shell operate the facility in accordance with the Technical Specifications.

3.

This license amendmsnt 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 N

IM R t.

f Suzanne ack, Assistant Director for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to tht: Technical Specifications Date of issuance:

July 20. 1988 6

_--_L

J c

ATTACHMENT TO LICENM AMEffFENT NO.122 FACILITY OPERATING mICENSE li0. DPR-68 DOCKET NO. 50-296 i

t i

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 amer.dment number and contain miarginal j

i j

lir.as indicating the area of change. Overleaf pages* are provided to maintain document completeness.

REMOVE INSERT l

3.7/4.7-13 3.7/4.7-13 3.7/4.7-14 3.7/4.7-14*

3.7/4.7-15 3.7/4.7-15 3.7/4.7-15a 3.7/4.7-15a 3.7/4.7-16 3.7/4.7-16*

3.7/4.7-19 3.7/4.7-19*

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3.7/4.7-20 3.7/4.7-20 s

l 1

_ __ _ _____ _ _____ ___ m

. ;a 3.7/4.7 C0!iTAIIMET'T SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B.

Standby Gas Treatment Systen 4.7.B. Standby Gas Treatment Systig

1a. Excapt as specified in 1.

At least once per year, Specification 3.7.B.3 below, the following conditions all three trains of the shall be demonstrated.

standby gas treatment system shall be OPERABLE at all a.

Pressure drop across times when secondary the combined HEPA containment integrity is filters and charcoal required.

adsorber banks is less than 6 inches of water lb. With no fuel in any reactor at a flow of 9000 cfm vessel, only two (2) of the (i 10%).

three (3) ste.ndby gas treat-ment trains are required b.

The inlet heaters on to be OPERABLE at all times each circuit are when secondary containment tested in accordance integrity is required.

If with ANSI N510-1975, either of the two (2) standby and are capable of an gas treatment system trains output of at least become inoperable at any time 40 kW.

When operability is required, suspend handling of irradiated c.

Air distribution is fuel until two (2) trains of uniform within 20%

standby gas treatment are across HEPA filters OPERABLE.

and charcoal adsorbers.

With no fuel in any reactor vessel, Specification 3.7.B.1.b is applicable.

BFN 3.7/4.7-13 Amendment No. 122 Unit 3 L

t 3.7/4.7 CONTAIfG2fEr SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B. Standby Gas Treatment Systen 4.7.B.

Standby Gas Treatment System

2. a. The results of the in-place

2. a. The tests and sample cold DOP and halogenated analysis of hydrocarbon tests at i 10%

Specification 3.7.B.2 design flow on HEPA filters shall be performed at and charcoal adsorber banks least once per operating shall show 199% DOP removal cycle or once every and 199% halogensted 18 months whichever hydrocarbon removal when occurs first for standby tested in accordance with service or after every ANSI H510-1975.

i'0 hours0 days 0 hours 0 weeks 0 months of system operation and 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 carbon sample analysis be performed after shall show 190% radioactive each complete or partial methyl iodide removal when replacement of the HEPA tested in accordance with filter bank or after any ASTM D3803 (130*C, structural maintenance 95% R.H.).

on the. system housing.

c. System shall be shown to

c. Halogenated hydrocarbon operate within 110% design testing shall be

flow, performed after each complete or. partial replacer.ent of the charcoal adsorber bank or after any structural maintenance on the system housing.

BFN 3.7/4.7-14 Amendment No. 114 Unit 3

a 3.7 /.'. 7 CONTAIf&ENT SYSTDiS LIMITIllG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B.

Standby Gas Treatment System 4.7.B. Standby Gas Treatment System 4.7.B.2 (Cont'd) d.

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

e.

Test sealing of gaskets for housing doors shall be performed utilizing-chemical smoke generators during each test performed for compliance with Specificatien 4.7.B.2.a and Specification 3.7.B.2.a.

3.

From and after the date 3.

a.

Once per operating cycle that one train of the automatic initiation of ste.ndby gas treatment each branch of the system is made or found standby gas treatment to be IN0PERABLE for any system shall be reason, reactor operation demonstrated from each and fuel handling is unit's controls.

permissible only during the succeeding 7 days unless b.

At least once per year such circuit is sooner made manual operability of OPERABLE, provided that the bypass valve for during such 7 days all active filter cooling shall be components of the other two demonstrated, standby gas treatment trains shall be OPERABLE.

c.

When one train of the standby gas treatment system becomes INOPERABLE the other two trains shall be demonstrated to be OPERABLE within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and daily thereafter.

Not applicable with no fuel in any reactor vessel.

BFN-Unit 3 3.7/4.7-15

T

2. 7 /'.7 ' CCriTAI!?ME!?T SYSTEMS c'

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B. Standby Gas Treatment System 4.7.B.

Standby Gas Treatment System 3.7.B.3 (Cont'd)

4. If these conditions cannot be met, the reactor _shall be placed in a condition for which the standby gas treatment system is not required.

l-BFN-Unit 3 3.7/4.7-15a i

s *y I

e t

i i

t t

TlfIS PAGE IITTEliTIOliALLY LEIT BLAfil; I

l

[

l l

l

3.7/4.7 CONTAINMENT SYSTEMS g

LIli1 TING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.C. Secondary Containment 4.7.C.

Secondary Containment

1. Secondary containment integrity

1. Secondary containment shall be maintained in the surveillance shall be reactor zone at :11 times performed as indicated except as specified in below:

3.7.C.2.

a. Secondary containment capability to maintain 1/4 inch of water vacuum under calm wind

(< 5 mph) conditions with a system inleakage rate of not more than 12,000 cfm, shall be demonstrated at each refueling outage prior to refueling.

2. If reactor zone secondary

2. After a secondary containment integrity cannot containment violation is be maintained the following determined the standby gas conditions shall be met:

treatment system will be operated immediately after

a. The reactor shall be made the affected zones are suberitical and Specification isolated from the remainder 3.3.A shall be met, of the secondary

' containment to confirm its

b. The reactor shall be cooled ability to maintain the down below 212*F and the remainder of the secondary reactor coolant system containment at 1/4-inch vented.

of water negative pressure under calm wind crnditions,

c. Fuel movement shall not be permitted in the reactor zone,

d. Primary containment integrity maintained.

3. Secondary containment integrity shall be maintained in the refueling zone, except as specified in 3.7.C.4.

BFH 3.7/4.7-16 Unit 3

if

+

) >

~3.7/4.7 CONTAfNMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.E. Control Room EmerRency Ventilation 4.7.E Control Room Emergency Ventilation

1. Except as specified in

1. At least once per operating Specification 3.7.E.3 below, cycle, not to exceed both control room emergency 18 months, the pressure drop pressurization systems across the combined HEPA shall be OPERABLE at all filters and charcoal adsorber times when any reactor banks shall be demonstrated to vessel contains irradiated to be less than 6 inches of

fuel, water at system design flow rate (i 10%).

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 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 af ter 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 110%

_ testing shall be performed design flow when tested in after each complete or accordance with ANSI partial replacement of the NS10-1975.

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 Amendment tb.114 Unit 3

\\

,4 3.7/4.7 CONTAINMENT SYSTEMS i

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 per operating one of the control room cycle not to exceed 18 months, emergency pressurization automatic initiation of the systems is made or found to control room emergency be INOPERABLE for any reason, pressurization system shall be reactor operation or refueling demonstrated.

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

l *

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 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 .

Open: FCO-151 FCO-152 s

f*LCOnotapplicablewithno l

fuel in any reactor vessel.

BFN-Unit 3 3.7.4.7-20 Amendment No. 122

. - _.

ML20151K739

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