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'' TENNESSEE VALLEY AUTHORITYCH ATTANOOGA. TENNESSEE 37 401

400 Chestnut Street Tower II

August 27, 1979

TVA BFNP TS 129

Mr. Barold R. Denton, DirectorOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory Cor: missionWashington, DC 20555

Dear Mr. Denton:

In the Matter of the ) Docket Nos. 50-259Tennessee Valley Authority ) 50-260

50-296

In accordance with the provisions of 10 CFR part 50.59, we are enclosing40 copies of a requested amendment to licenses DPR-33, DPR-52, and DPR-68to change the technical specifications of the Browns Ferry Nuclear Plantunits 1, 2, and 3 (Enclosure 1). These proposed changes concern thehigh drywell pressure trip level setting. The proposal providesadditional operational margin without producing a degradation of safetyfunctions. Justification for the proposed trip level setting change isincluded as Enclosure 2.

In accordance with the requirements of 10 CFR Part 170.22, we havedetermined these proposed amendments to be Class III for unit 1 and Class Ifor units 2 and 3. These classifications are based on the facts thatthe proposed amerdment for unit 1 involves a single safety issue whichdoes not involve a significant hazard consideration and the proposed amend-ments for unita 2 ar.d 3 are duplicates of the unit 1 proposed amendment.

The remf.ttance for $4800 ($4000 for unit 1 and $800 for units 2 and 3)ia being wired to the NRC, Attention: Licenoing Fee Management Branch.

Very truly yours,

TENh SEE VALLEY AUTHORITY

%s. M.' Mills , Ma ger

Nuclear Regulation and Safety

Subscribed and sworn to beforeme this 2 '7 day of [////j// J81979.WI f'

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v / M .W i ?All(|[Vl 'c ( LNotary Public dMy Comission Expires {[Y. /! Nh/ 3090d 7Enclosurescc: See page 2

An E qual Opportunity Employer

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Mr. Harold R. Denton August 27, 1979

cc (Enclosures):Mr. Charles R. ChristopherChairman, Limestone County ComissionP.O. Box 188.ithens, Alabama 35611

Dr. Ira L. MyersState Health OfficerState Department of Public HealthState Office BuildingMontgomery, Alabama 36104

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TAILE 3.2.A ,

FXIMARI CONTAI!OiDIT AND RfACTC1 BU*IIING IS0tATION INSTWMDfIATION

bain % No. .

Operable ForTrip Sys (t) Funettoa Trip tevel Setting Action (1) ' Remarks

1 Instrusent Chacac1 - 1 53D" above vessel tero A or 1. Eclow trip setting does the _

teactor Im Vater level (6) (8 and E) following:e. !attistes 34 actor So11 ding

Isolettoob. Initiatee Primary Coctaircoent

Isolaeton,,

c. Tottistes SCTS ,

C3 1 Instrt_ ment Chann=1 - 100 + L5 pais D 1. Above trip setting isolates the

1 Emactor High Pressure shutdown ecollag suctDra. valvesof the 211 system. 3

> > Z Instraeot Channel - 3 + 7o * ab<,ve ve s s el t e ro . A 1. Below trip setting inittates Main

teactor ta voter Level Scena Lins Iniscionr mU * (LIS-3-56A-o, Su di)

A or 1. Above trip settins does theZ Instrument channel - < 2.5,s:3ui h Dryv 11 Presoure (6) (3 and 2)- following:t ,g(FS -4 4 -5 6 A-D) a. Initiates Ra. actor EuL1 ding

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b. InitLates Primary Containnent

b Iso 14tica,

' c. Inftiates SCTS

2 Instr - t otsonel - e_ 3 times normal rated B 1. Above trip setting initiates Main

High b 41stion Kata Steam full power background. Steam Line IsolationI.ine Tuanal (6)

2 Insttv w nt Channel - 1825 Psts (4) B 1. Below trip settins initiates Main@ Low Pressure Main Steam Steau Line Isolation

C Line

OQ 2(3) Ins t r tne nt Channel - ._ 14cI of rated steam flow 3 1. Above trip settins toitiates Male

Steam Line Isolettoop2 UIgh flow Mato Stema Line

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TAILE 3.2.AFRDtARY CDNTAIMMDff AND REACTOR BUILDING 1501Att0N INST 1ttMDfTATTON

Minimum No. ,

operable ForTrip Sys (1) Function Trip favel Setting Action (1)_ Remarks

2 Instrument Channel - 3,338" above vessel cero A or 1. Below trip setting does the ,

taactor low Water level (6) (3 and E) following;;

s. Initiates Keactor So11 ding

Isolationb. Initiates Faimacy Cootalament

Isolation,

c. Inittet.a SCTS ,

1 1 Instrunest Chann=1 - 100 + 15 pois I, 1. Above trip setting isolates the

(_- Imactor High Freasure shutdown cooltag suctina valvesof the EER system.

2 Instrument Channet - 3 47o'above veasci sero. A 1. Below trip setting initiates Katatractor low Vater tevel Steam Line Ioslation, ,

m* Q.IS-3-56A-o, SU di)

' (' ) 2 Instnzment Channel - 1 2.G a s;3 A or 1. Above trip setting does the'

f High Dryve11 Frescars (6) (5 and E)- following: ,

Initiates R4 actor Building(F5-44-56 A-D) a.Isolation

> b. Init14 tee Primary Containment' Isolationy' ' c. Initiates SCTS

2 Imatrument Channel - 3 3 times normal rated B 1. Above trip setting initiates Main

High Radia:,1on Main Steam full power background Steam Line IsolationLine Tunnel (6)

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2 Instrument Channel - 1825 psig (4) 'S 1. Below trip setting initiates Main

@ tow Pressure Mata steam Steam Line Isolation

Q Line ,

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_ 140% of rated steam flow 3 1. Above trip setting intetstes Main~

$ 2(3) Instrument Channel - <

Steam Line IsolationHigh Flow Main Steau LineyO

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ENCLOSURE 2

REASONS AND JUSTIFICATIONS FOR PROPOSEDCHANGES TO BROWNS FERRY NUCLEAR

PLANT TECHNICAL SPECIFICATIONS FORUNITS 1, 2, AND 3

UNIT 1

Page 55 . . . . . It is proposed to change Table 3.2.A: " InstrumentChannel - High Drywell Pressure (6) (PS-64-56A-D)"trip level setting from ."g2 psig" to ."f 2.5 psig."This change would provide additional operationalmargin without producing a degradation ofsafety functions. Instrumentation would bemore reliable with greater span to use incalibration and functional checks. This changeis similar to a change approved by the NRC onFebruary 7, 1978, for Vermont Yankee.

Evaluation

The high drywell pressure trip signal is used toinitiate primary containment isolation and servesas a backup or conjunctive signal to initiatethe ECCS, With respect to the time to achievecontainment isolation, the performance of theECCS, and contairment response to a postulatedLOCA, the following is presented. The higherinitial containment presaure will slightlyimprove ECCS pump performance due to the smallincrease in the net positive suction headaccompanied by a lesser increase in pump dischargepressure. In addition, the change in thecontainment isolation time and the containmentpressure response will be small since they areprimarily a function of the differecticipressure from dt'well ambient and the trip setting.The margins between the containment design pressureand temperature and the calculated results fora spectrum of breaks is sufficiently large toaccommodate the small changes assoc ated withthe higher setpoint. Fuel peak clad temperatureswould be unaffected in the event of the designbasis accident by the propssed 0.5 pai tacrease incontainment ambient pressure as the rate ofdischarge from a postulated double-ended piperupture would be at choked-flow conditions andindependent of discharge pressure.

UNIT 2

Page 55 . . . . . Same as page 55 for unit 1 above,

UNIT 3

Page 57 . . . Same as page 55 for unit 1 above.. .

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