ML20100M935

Amend 84 to License DPR-68,changing Tech Specs to Reflect Deactivation of Reactor Vessel Head Spray Piping

ML20100M935
Person / Time
Site:	Browns Ferry
Issue date:	11/26/1984
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Tennessee Valley Authority
Shared Package
ML20100M939	List: ML20100M935 ML20100M957
References
DPR-68-A-084 NUDOCS 8412120512
Download: ML20100M935 (6)

Text

UNITED STATES

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[g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 s; o j 1

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. DPR-68 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee)datedMay 10, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

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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 ce 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.

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. 84, are hereby incorporated in the license.

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

8412120512 841126 PDR ADOCK 05000296 P

PDR '

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3.

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

FOR THE NUCLEAR REGULATORY COM4ISSION yk(p.y.t Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 26l 1984 O

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j ATTACHMENT TO LICENSE AMENDMENT NO. 84 FACILITY OPERATING LICENSE NO. DPR-68 l

DOCKET NO. 50-296 Revise Appendix A as follows:

1.

Remove ~the following pages and replace with identically numbered 1

pages.

I 262, 269, 280 l

2.

The marginal lines on these pages denote the area being changea.

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Ta2LE 3.1.A rpIMAaY mittA1G4 INT I:nL.ATIcas vALvts Actims on etasteum opesatcJ valves operating Horsal Init iat t at 3=

Wester of Fuwer 51 Ir. lea s 4 OutleasJ Tsee (sec.3 Fosstion St.gnal 8D

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Valve Identa tication A'

Gaoep e

e 2CTC 5 0

g stain steastine isolatto.s watwee eu 3

1 f rCV-t-lo. 26, 31, 5 55; l-15, 21. 3e s 523 0

CC 1

1 15 o

36ain steamline drain tentation 1

valves trev-t-55 8 l-56 1

1 5

c sc 1*

seaceor water sample 11ae isota-tion valves se asas shutdown cooling espp1r 1

1 es c

2 S eolation salves trcv-to-se 6 eil sc 2

30 c

a3 b

2 suas - LPC1 to reactor trcy-14-53 & 613 sc 2

asas ilush and. train went to 20 e

e 5

ouppresoton cassW e lrcv-le-102 103, 119, & 120) 2 15 0**

GC 2

soprzeselon chamber Orsin t ecv-15-51 6 543 0

cc 2

Drywell equipment drals. diecharge 2

15 toolation valve (rcy-11-ISA 8 Sal 2

Drywell Stone dsato dischgrge 2

15 e

CC isolation valves trev-11-2A C 233

• These valves isolate only on reactor vessel low low water level (470") and snain steam line high radiation of Group 1 la.olations.

• • These valves are norina11y open when the pressure suppression head tank is aligned piping and closed when the condensate head tank to serve the RIIR and CS discharge (See Specification 3.5.11) is used to serve the RilR and CS discharge piping.

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TABLE 3.7.C r

TESTABLE PEN!.'TRATICtf3 WITE TESTABLE BELIDMS X-7A Primary Steamline 2-11 Steamline to EPCI Turbine X-78 Primary stealine x-12 RER Shutdown Supply Line X-7C Primary Steamline 2-13A RER Return Line X-70 Primary steamline 2 133 RER Return Line X-8 Primary steamline Drain 2-14 Reactor Water Cleanup Line 1

X-9A Peedwater Line 2-14A Core Spray Line X-9s Peedwater Line 3-163 Core Spray Line X-10

. steamiime to RCIC Turbine 2-17 Blank 1

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Amendment No. 84 269 l

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g TABLE 3 7.F PRrWLY CottfAIt32iiT ISOIATION VALVES LOCATID I:(

UATIR SIAIID SEIS!4IC CIASS 1 LUIS Valve Identifientio'n V31ve k

R!E I.ICI Diseborge 7 -53 7h-54 It!R 7 -57 RHR Suppression Cha:aber Spray 4

74-58 RIE Suppression Chamber Spray 7h-60 RHR Drywell Gpray Th-61 R1R Drywell Spray 78-67 Rim LICI Discharge 1

Th ')8 RHR LICI Discherge "h*71 R:R Suppression Chamber Spray

86 - 7 2 RHR Suppression Chamber Spray 7k ~k R1R Drywell Spray

?t.75 RHR Drywell Spray i

75-25 Core Spray DLacharge 75-25 Core Spray Discharge e

75-53 Core Sprey DLscharge 75 5h Core Spray DischarCe s

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O e

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280 Amendment No.

84

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