ML18025B934

Amend 88 to License DPR-33,changing Tech Specs to Allow Operation W/Increased Core Flow During Remainder of Cycle 5

ML18025B934
Person / Time
Site:	Browns Ferry
Issue date:	03/14/1983
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Tennessee Valley Authority
Shared Package
ML18025B935	List: ML18025B934 ML18025B936
References
DPR-33-A-088 NUDOCS 8303300228
Download: ML18025B934 (8)

Text

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTOhl,D. C. 20555 TENNESSEE VALI.EY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-33 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated February 1, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission'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 Commission; C.

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

The issuance of this amendment will not be inimical to the common defense and secur ity 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 Commissfon'.s regulations ahd all applfcatfle requirements have been satisfied.

2.

Accordingly, the license fs amended by changes to the Technical. Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facflfty License No. DPR-33 is hereby amended to read as follows:

(2)

Technical S ecificatfons The Technical Specifications contained fn Appendices A and B, as revised through Amendment No. 88, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specfffcatfons.

8303300228 8303i4 PDR ADQCK 05000259 I

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

l FOR THE NU AR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 14, 1983 Domenic B. Vassal o,

hief Operating Reactors Branch 82 Division of Licensing 4

ATTACHMENT'TO LICENSE'AMENDMENT NO. 88

'FACILITY'OPERATING'LICENSE NO 'DPR-33

'DOCKET'NO: 50-259 Revise Appendix-A as follows:

1.

Remove the following pages and replace with identically numbered pages:

73 75 172b 173 2.

The marginal lines on these pages indicate the revised area.

Q TAB@ 3.3oc THSTROKKrTATIOH TOST bl?TIATES ROO BLOC<5

}un)sue Ho.

operable Psr

~tl s

5 3 {1) 3 (1) tunct ion Ap}u( Opsca1 ~ {tla Blas)

APRN Opscale (Startup node)

(6)

Attic Damscs le

{5)

AP}u{ laoperatlie REs( Opscale (tlav Bias)

~ Dounsca le

{9)

RBa Tooperatlse t}U( Opsca le (6)

I}u( Downscale

{3) (6)

Ti'll5 tQ

~0 ~ Cavo a)5 (3)

~ 135

~35 (10b)

< 0 CQtta05

{3) (13)

+ 35

'(10c)

~ 106/13$ ot tall scale

+ S/)3$ ot tull scathe 3 (1) 3 (1) 3{'I) {6) 3(1} (6) 3('1) (6) 3(1) (6) 3(1}

h IAN Detector not ln Startup Posltlon

)BX Inoperatlee (Bl SRN Opscsl e

{6)

" SR}1 Downscale

( ~ ) (6)

(6)

('l1)

(104) c 1 I 10 coun'ta/ssc

~

3 couats/sac.

tlcw Bise cospsrstor ties Blas Opscale Rod Block to0{c

~ 105 dlttarancs la rsclrculatlon tines

< 115% recirculation flow S/A sR}1 Detector not ln Stsrtup tosltlon

{a) (4)

(11)

BR}l tnoperatlse (6)

(10 ~ )

SSCS Sestrs(at (PS-IS C1A and PB 6$

C1B) lal ps10 turbine first-stsSe pressure 1(12)

Scratu Discharge Tank Mater Level ))fgh

<25 gal.

$ ~

Thia Cunct ion is byps ~ sad vhan the eada ovitch is placed in Run.

9.

Thio Cunct ion Is only nccivo vhan tho endo sricch is in Run.

This tuner ion Ih sutoast ically bypassed vhon tho LBt Lnocwiancation io operable and not high.

10.

Tha inoperative trips arc produced by tha Colloving Cunctiona

~

SIIK and IR.K (1)

Local "oporatawalibrate" svitch noc in oporat ~.

(2)

Poor supply volcago Lou.

(2)

Circuit boards not in circuit.

b.

APtuI (1)

Local "operaco-cslibrac ~" svitch not Ln oparata.

(2)

Lass chan l4 Lptul Lnputo.

(2)

Circuit bosrdo rot in circuit.

c.

RgH (1)

Local "operate-calibrato"'avitch not in oparate,.

(2)

Circuit boarda not in circuit.

s (2)

RSH Cail ~ to null.

(4)

Laaa chan required nunber oC LFIQI inpuca Cor rod oolocted.

+

11 ~

Detector traverse Ls ad)usted to 114 - 2 Lnchea, placing tho detector lover position 24 Lnchea bolov tho lover coro plato.

12.

This function may be bypassed in the shutdown or refuel mode.

If this function Ls inoperable at a time Mhen operability is required the channel shall be tripped or administrative controls shall be immediately imposed to prevent control rod Mithdraval.

l3.

RBM upscale flow biased setpoint clipped at 106X rated reactor power.

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0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7:

0.8

'. 0.9 1.0 Figure 3.5.K-1 MCPR LIMITS*

>NOTE:

Lead test assemblies are categorized as PSxSR bundles.

172b Amendmenf No, 7tt 88

BROOMS FE::.".Y NUCLEAR PLANT FlGURE 3 5.2 Kl FACTOR l.2 AUTOMATIC FLOW CONTROL l.o QANUA1 FLOW CONTROL Scoop-Tube Sot-Point Calibration position such that Ffowmox

= loX5 A I O7.0 'I Ito.o'l.~

Itv.D'/.

30 40 50 60 70 CORE FLOE,N 80 90 l00 *

• Kf ~ 1.0 for core flow > 100X.