ML18031B022

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Amends 130,126 & 101 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Deleting Tech Spec Refs to Charcoal Filter Heaters in Standby Gas Treatment Sys
ML18031B022
Person / Time
Site: Browns Ferry  
(DPR-033, DPR-052, DPR-068)
Issue date: 11/17/1986
From: Muller D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML18031B023 List:
References
DPR-33-A-130, DPR-52-A-126, DPR-68-A-101, TAC-61532, TAC-61533, TAC-61534 NUDOCS 8611210254
Download: ML18031B022 (30)


Text

f UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROMNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. y3p 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 April 8, 1986, 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 health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the, common 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 Commission's regulations and all applicable requirements have been'atisfied.

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-33 is hereby amended to read as follows:

ADOCK 05000259 b11210254 Bbii17 PDR P

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2 (2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

130, 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 the date of issuance and shall be implemented within 90 days from the date of issuance FOR THE NUCLEAR REGULATORY CON ION A'i~~

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 17, 1986 Daniel R. Muller, Director BWR Project Directorate ¹2 Division of BWR Licensing

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ATTACHMENT TO LICENSE AMENDMENT NO.

130 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.

Pa<aes 56 86 2.

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

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o Instrument Cltnnne] 0 0!ieroble

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~l..tti Artion~l Thl)I.E 3. 2. A PRIHARy ColiTAIHHIITAHD RrhC t~ll lnlll.lllno lsolATIOI'I>STRUIIVIITATIoII Remarks 2 (12) lnotrument Channei-llain Steam Line Tunne)

High Temperature

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Instrument Channel Reactor Mater Clea iup System Ploor Drain High Temperature Instrument Channel Reactor Mater Cleanup System Space Hiqh Temperature Instrument Channel Reactor Building Venti-lation High Radiation-Reactor Zone

< 200or Iba 1004F lb0 -

1804F 100 nr/hr or dovnscale O

Above trip settinn Inxtiatcs Ilaln Steam Ltne Iso) gati< n.

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n.uvv t c 1! ~ "et t 1 t il ln) t fates

'. IoiltlJn

>f Reactor Rater C.'conn!

Llb from Reoctnr a:~3

.=eactur leer Return Line.

I, i.'le as a.',Jvc upscale or 2 dovnscale vill Insatiate SOTS t.

Isolate reactor

=one and retuel inq floor.

c.

Clos>> a-oosphere control aystc~.

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Instrument Channel Reactor Building Venti-lation Uiqh Radiation Refueling Zone 160 mr/hr or dovnscale F

1.

I upscale cr 2 dcvnscale vill a.

In'. iate SOTS I olat~ refueltng floor.

c.

Close atmosphere control ay"tcm.

2 {7) 18)

Instrument Channel SOTS Flov - Train A Heater R.!I. I!eater.

S 2000 cfm H and (A or F) 2elav 200: Cfm, l.rip Settinq R.II.

heater vill shut off.

2(>) IB) 2IT) I8)

Instrument Channel SOTS Plow - Train 8

Heater Instrument Channel SOTS Flov - Train C Heater R.H. Heater S 2000 cfm R.H. Ileater 5 2000 cfm H and IA or F)

H anil IA or.F)

-"clou 2t00 cfm, trip setting R.!!.

heater vill st:ut off.

~elov 200G cfm trap "et.t anq

~ II Ieater vill nut oil.

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2 ~ A SmrVEILLAHCE RIX)OIREHEHTS FOA irAIHAAT COHTAIHHEHT AHD AD4CTOA BUILDIHO ISOLATIOH IHSTAOHEHTATIOH u 'tl Instcusent Channel Aeactoc Bu()d(nr) Ventllatlcn Bigh Radiation - Aefuellnr) Zone Instcusent Channel SOTS Tcain A Hester Unct 0

a cat

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Cs) )brat)on r

uen once/ 3 aontha nst rue ent Cbec)r once/dsy (r))

H/A Inatzrrnent Channel-SCTS Train 8 Heater Instrunent Channel SOTS Train C Beater Reactor Bui)d (nr) Isolation T(sec (re fuel (rrr) Iloor)

(4) la) once/operatlny cycle H/A Resctoc Bui)dlnr) Isolation Tiner (reactor

zonei, (a) once/opecatiny cycle H/A

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

>26 License No.

DPR-52 h

1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated April 8, 1986 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 health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common 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 Commission'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-52 is hereby amended to read as follows:

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(2)

Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 126

, 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 the date of issuance and.shall be implemented within 90 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMI SION

&777 Daniel R. Muller, Director BWR Project Directorate ¹2 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 17, 1986

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ATTACHMENT TO LICENSE AMENDMENT NO. 126 FACILITY OPERATING LICENSE NO.

DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:

Remove the following pages and replace with identically numbered pages.

~Pa es 56 86 2.

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

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Instrument Cltan>>cl Operable r~cr Trl

> S,s(1)[t Jl Tnnt.e 3.2.h PRIHAIIY COttTAI:tH tlT A!tD RFAC&tt UUII,DIWG ISOIATIOt: IIIGTRUHHWTATIOII Tri Iwvrl Set tin Pemr rks

-'12)

Instrument Channel Hain Steam Line Tunre)

High Temperature c

20001'.

Above trip set tir>n initidt 0 train Gtedm Lane I snlat ir n.

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(] ~r )

Instrument channel Reactor Mater Clea iup System Ploor Drain Hiqh Temperature Instrument Channel RedCtOr ltater Cleanup System Space lligh Temperature Instrument Channel Reactor Building atcnti-lat ion Hiqh Radia taon-Reactor Zone Instrument Channel-Reactor Building Venti-lation High Radiation-Relueling Zona!

Iba - 1804F IbQ -

1804F 5

100 nrrhr or downscale G

100 mr/hr or downscale 1

n.uvv a rat ~ "eta if>~1 arri t id'teS

! =-oiati or if Reactor Mater C vorurp Lai ~

ft om Rcactot a:i3

.=eictur Ma!cr hcturn Linc.

>we s.r'..ovc 1.

1 upscale or 2 downscale uil1 In at a at c SG'I S b.

Isolate reactor onc and relueling floor.

c Clos~ atoosnhcre control system.

1.

I upscale or 2 downscale will Initiate SGTS Isolate refuelanq floor ~

c.

Clo=c atmosphere control system 2 (7) (8)

Instrument Channel SGIS Flew - Train A

Heater R..'I. Iledter 5 2000 cfm H and (h or F)

Below 20J: cfm, trip setting R it.

heater uill shut off.

2 (7) (8)

Instrument Channel SGTS Plow - Train B

Heater H and R.H. Heater 5 2000 cfm (h or F)

Below 2C30 cfm, trip setting R.!I.

heater will shut off.

2 (7) (8)

Instrument Channel SGTG Flou - Train C

!leat er R.H lleater 5 2000 cfm H dn)

(h or F) dr tow 2000 elm trip sett ang

~ II t eater wall nut ot t.

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TAOIS ~ ~ I.A 50QVEIfLAHCE RR)OIBEHEHTS FOA PAIHAAY COQZAIHHEHT AHD AEACTOA BUILDIHC ISOIATIOH IHSTAOHEHTATIOH

~~a Inetsuscnt Channel-Acactor Building Vcntllet lcm Bigh Aadiation Actual lng Ecne Inatruaent Channel-SCTS Train A Beater f~sct jo~Laa ')'est tl) t>4) )32)

(4)

Ca) lb ation Fr ucn once/3 aonthe Instruecnt Cbcck once/day

{4)

Inatnuacnt Channel-SCTS Train B Beater Inetruacnt Channel-SCSS Train C Bcatcr Aeactor Building Isolation Tincr (rctueling tioor) te) t4) t4) once/operating cycle H/A Aeactor Building Isolation Tieer {reactor conc)

(4) once/operating cycle

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROMNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

101 License No.

DPR-68 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated April 8, 1986 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 health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common 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 Commission'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:

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Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 101, 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 the date of issuance and shall be implemented within 90 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director BWR Project Directorate 82 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

~ November 17, 1986

t A /

s I

ATTACHMENT TO LICENSE AMENDMENT NO.

101 FACILITY OPERATING LICENSE NO.

DPR-68 DOCKET NO. 50-296

.Revise Appendix A as follows:

1.

Remove the following pages and replace with identically numbered pages.

Pa<aes 58 89 2.

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

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]nstrument C)1IInnuls C) crnble

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~J TAIII.P.I ~ 2 ~ A PHLHAHY CVIITAIIII~IIT uo BIACll)ll UHIIIIltIG I'4>)ATIOII LII TRIIIIEIITATIMII Tri hevrl Sct tin~

ActInn~I]

Rem> res

(]4)

Instrument Channe)

Reactor Mater Clea nup System Floor Drain I)igh Temperature Instrument Channel Reactor Water Cleanup System Space )lich Temperature Instrument Channel-Reactor Building Venti-lation High Radiation-Reactor 2one Instrument Channel-Rc ctor Building ucnti-lation High RadiatLon-RefueLing 2onc Ibo -

IOOOF Ibo - 1800F 5

IOO mr/nr or dovnscalc 100 mr/br or dovn sea le F

I ~

n'.vvv t t lie Sett 1

( 0 lnlt latCS

'. zos atl.n

)f Reactor water 0'onup Li<.

ft om Reactor an)

) c)ctur

".er Return Linc I.. ice '".i: uvc up sea Le or 2

dovnsca le vi LI Inataatc SGTS h.

Isolate reactor one and rcluclinq floor.

c.

Close atmo chere control sy tc~.

1.

1 upscale cr 2 dcvnscalc vill a.

Initiate SOTS s..

) o)ate refueling floor ~

c.

c.lose ataospht rc control system 2 (>) lo)

Instrument Channel SGTS Flov - Train A Heater R.H. Heater S 2000 cfm H and IA or FI Bclov CQ ': cfn, trip setting R.il.

heater vilL stiut off.

2{2) fO) 2l>) (8)

Inctrurent Channel SGTS Flov - Train B

Heater Instrument Channci SGTS Flov - Train C Heater R.H. I)eater S

2000 cfn R.H. Heater 5 2000 cfm H and (A or F)

H an)

IA or F)

"clov 2CQO cfm, trip setting R.II.

heater vi)L st:ut oft.

~e)ov 200G clm, trap sett ang R.II.

heater vt)L Shut Olt

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TABLE ~,2 A SNlVEILLANCC RSQQIRIXESTS D'OR tRIlULRT COMThININrt AHD REACTOR SVILOIHG ISOLATICN INSTRUNENthTIee Inatrueent Channel-Reactor Building Ventilatica Sigh Radiation - Refueling Xcee lnatrescnt Channel SCTS Train A Seater.

Inatruncnt Channel <<

scrs Train B Beater Inatruncnt Channel-SCTS Train C Beater Reactor Building Isolation Tbser (refuel fng floor) lI) t )al f22) lal h htiocl r

uen orna/3 aonthe once/operating cycle Inetrusaant Cheek once/day (S)

WA Reactor building Ieolatioa Tinsr )reactor sono) once/operating cycle

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