ML20069Q441
| ML20069Q441 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/03/1991 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069Q443 | List: |
| References | |
| NUDOCS 9101160045 | |
| Download: ML20069Q441 (15) | |
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UNITJD sT ATEs l ' 3 v#c/[,,g NUCLE AR REGULATORY COMMISSION 4
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TENNESSEE VALLEY AUTHORITY j
DOCKET NO. 50-259 i
i BROWNS FERRY NUCLEAR PLANT. UNIT 1 i
AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No.178 License No. DPR-33 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:-
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 4,1990 as supplemented October 24,=1990, 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 f acility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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 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.
910.1160045 910103 PDR ADUCM 05000259 P
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2.
Accordingly, the license is amended by changes to th'e 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:
(2) -Technical Specifications The Technical Specifications contained in Appendices A and B, as_
l revised through Amendment No. 178, are hereby incorporated in the-licente. 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 implemented within 30 days from the date.of issuance.
FOR THE NUCLEAR REGULATORY COMNISSION Mb Frederick s1. Heb on, Director Project Directorate 11-4 Division of' Reactor Projects _- 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of._ Issuance: January 3, 1991 l
ATTACHMENT TO LICENSE AMENDMENT NO.-- 178 l
FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Revise the Appendix A Technical. Specifications by removing the pages identified below and inserting the enclosed-pages. The1 revised ; pages are identified by the. captioned amendment number _and contain marginal lines indicating the area of change.
i REMOVE INSERT 3.1/4.1 -1
. 3.'1/4.1 -1 3.1/4.1-2
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1 1/4.1 REACTOR PROTECTION SYSTEM 1.!MITING CONDITIONS POR OPERATION SURVEILLANCE REQUIREMENTS 3.1 Reactor Protection Svetem 4.1 Ein.s. lor Protection System Aeolicabilit.y
&oolicability Applies to the instrumentation Applies to the surveillance and associated devices which of the instrumentation and associated devices which' initiate a reactor scram, initiate reactor scram.
Objective Objective To assure-the OPERABILITY of the To specify the type and reactor protection system.
frequency.of surveillance to-be applied to the protection instrumentation.
SPE lfication goecification A.
When there is fuel in the vessel, A. Instrumentation systems shall the setpoints, minimum number of be functionally tested and-trip systems, and minimum number calibrated as indicated in of instrument channels that must Tables 4.1.A and 4.1.B, be OPERABLE for each MODE of respectively.
OPERATION shall be as given in Table 3.1.A.
B.
Two RPS power monitoring channels B.
The RPS power monitoring l
for each inservice RPS MG set or system instrumentation shall alternate source shall be OPERABLE.
be determined OPERABLE 1.
With one RPS electric power 1.
At least once per monitoring channel for 6 months by performance
. inservice RPS MG set or of channel functional alternate power supply tests.
l
-inoperable, restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS MG set or alternate power supply from service.
BFN 3.1/4.1-1 Amendment 178 Unit 1
A.1/4 1 REACTOR PROXECTION SES.IEM
(
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS-3.1 RfAgipI Protection System' 4.1 Reactor Protection Sysigm
-3.1.B. (Cont'd) 4.1.B. (Cont'd) 2.
With both RPS electric power 2.-
At least once per'18 months monitoring channels for an by demonstrating the OPERA-inservice RPS MG set or BILITY_of overvoltage, under-alternate power supply _
voltage and underfrequency inoperable, restore at least protective instrumentation _by I
one to OPERABLE status within simulated automatic logic 30 minutes or remove the actuation and verification of associated RPS MG set or the circuit protector-trip alternate power supply from level setting as follows, service.
(a) overvoltage 1 132.0 VAC (b) undervoltage 1 108.5 VAC (c) underfrequency 1 56.0 Hz 1
BFN 3.1/4.1-2 Amendment 178 Unit 1
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TENNESSEE VALLEY AUTHORITY
@CKETNO.50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.184 License No. DPR-52 1.
The Nuclear Regulatory Comission (th: Conmission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 4,1990 as supplemented October.24,1990,_
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended hhe 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 (1) 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 coman 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.
1
-2.-.
j
- l 2.
Accordingly, the license is amended by changes to the' Technical-Specifications as indicated in the attachment to this license amendment-and paragraph.2.0.(2) of Facility Operating License No. DPR-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.184, 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.fte of issuance and~shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
. 4 1
WYL Frederick J. He don, Director Project Directorate 11-4 Division of Reactor Projects.- 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:. January 3. 1991 t
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ATTACHMENTTOLJCENSEAMENDMENTNO.184 TACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 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 amendment number and contain marginal lines indicating the area of change.
R[ MOVE INSERT 3.1/4.1 -1 3.1/4.1-1 3.1/4.1-2 3.1/4.1-2 l
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$1/4.1 REAGTOR PROJEfJION SYSTrd LIMITING CONDITIONS FOR OPERATION SJRVEILLANCE REQUIREMENTS 3.1 Ettetor Prq11etien Svetem 4.1 Reattor froltation_Sya.11m Apuliuhtli_ty ApslinhilitY Applien to the instrumentation Applies to the surveillance and associated devices which of the instrumentation and associated devices which initiate a reactor scram, initiate reactor scram.
Objective Objectlyg To assure the OPERABILITY of the To specify the type and reactor protection system.
frequency of surveilleAce to be app'ted to the protection instrumentation.
apecificat12D inggification A. Instrumentation systems shall.
f A.
When there is fuel in the vessel, the setpoints, minimum number of be functionally tested and trip systems, and minimum number calibrated as indicated in of instrument channels that must Tables 4.1.A and 4.1.B.
be OPERABLE for MODE OP OP RATION respectively.
shall be as given in Tab'4e 3.1. A.
3 B.
Two RPS power monitoring channels B. The RPS. power monitoring l
for each inservice RPS MG set or system instrumentation shall alternate source shall be OPERABLE.
be determined OPERABLE:
1.
With one RPS electric power 1.
At least once per monitoring channel for 6 months by performance inservice RPS MG set or of channel functional alternate power supply tests.
inoperable, restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove l
the associated RPS MG set or alternate power supply from service.
j l
l BTN 3.1/4.1-1 Amendment 184 Unit 2 r
. _ _. _ _ _. _ _ _.. _. _ _. _. _. _. _. _ _ _ ~. _ _ - -. ~. _..
l-L1/b1 REAGIOR PROTEC.IIAN SYSTEM t,IMITING CONDITIONS T0.1 OPERATION SlfRVEf t, LANCE RTOUIREMENTS
[
3.1 Rueter rrsteetiottJ.xsirg 4.1 Ru.c. lor. Protection System f
3.1.B. (Cont'd) 4.1.B. (Cont'd) l 2.
With both RPS electric power 2.
At least once per 18 months monitoring channels for an by demonstrating the OPERA-inservlee RPS MG set or h!LITY ei overvoittge, under-alternate power supply voltage and underfrequency inoperable, restore at least protective instrumentation by i
j one to OPERABt.E status within simulated automatic logic j
30 minutes or remove the actuation and verification-of 1
.nssociated RPS MG set or the circuit. protector trip i
alternate power supply.
level' setting as follove.
j from service.,
(a) overvoltage
,1 132.0 VAC i
j (b) undervoltage 1 108.5 VAC i
(c) underfrequency.1 56.0 Hz I
1 1
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i BTN 3.1/4.1-2 Amendraent 184 Unit 2 l
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NUCLE AR REGUL ATORY COMMISSION l
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TENNESSEEVt/LEYAUTHORITY j
DOClitT NO. 50-296 l
BROWNS FERRY NUCLEAR PLANT. UNIT 3 l
AMENDMENT TO FACILITY OPERATING LICENSE j
i Amendment No.149 License No. DPR-68 1
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley A.tbority (the licensee) dated June 4, 1990 as supplemented October 24, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and j
regulations set forth in 10 CFR Chapter It 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 safety of the public, and (ii) that such activities will be i
conducted in compliance with the Comission'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 publict and E.
The issuance of this amendment is ia accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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2 i
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-6B is hereby amended to read as follows:
4 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.149, are hereby incorporated in the i
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 oe implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMM'!$510N
-I i
Mjb
.0 s
Frederick J. Hebdon, Director Project Directorate 11-4 Division of Reactor Projects - I/11 Office of Nuclear Reactor _ Regulation
Attachment:
Changes to ths Technical Specifications Date of 1ssuance: January 3,1991 4
I 5
l 1
ATTACHMENT TO LICENSE AMENDMENT N0.149 FACILITY OPERATING LICENSE NO. OPR-68 DOCKET NO. 50-296 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 amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.1/4.1-1 3.1/4.1-1 3.1/4.1-la
1 3.1/4.1 R.EASTOR PROTECTION _SYSTEtj LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.1 Rtector Protection System 4.1 Etatt e r Prot e c tion Sv_girm J
AtDiltahlliix Ann 11embilitv Applies to the instrumentation Applies to the surveillance and associated devices which of the instrumentation and initiate a reactor scram, associated devices which initiate reactor scram.
Q),ig11Jvg Objective To assure tha OPERABILITY of the To specify the type and reactor protection system.
frequency of surveillance to be applied to the protection instrumentation.
Entrif.lta W n 19eeifieatinn A.
When there is fuel in the A.
Instrumentation systems vessel, the setpoints, minimum shall be functionally number of trip systems, and tested and calibrated as minimum number of instrument indicated in Tables 4.1.A channels that must be OPERABLE and 4.1.B respectively.
for each MODE OF OPERATION shall be as given in Table 3.1.A.
D.
Two RPS power monitoring channels B.
The RPS power monitoring for each inservice RPS MG set system instrumentation shall or alternate source shall be be determinad OPERABLE:
1.
With one RPS electric power 1.
At least once per monitoring channel for 6 months by performance inservice RPS MG set or of channel functional alternate power supply inop-tests.
etable, restore the inoper-able channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS MG set or alternate power supply from service.
l BFN 3.1/4.1-1 Amendment 149 Unit 3
j.1/4.1 REACTOR PROTECTION SY9 TEM LIMITING CONDITIONS FOR OPERATION SURVEILt.ANCE REQUIREMENTS 3.1 React or P.tgitc.tintL&yAt.tp 4.1 RtJLC191.I.T.flection Syst em 3.1.B. (Cont'd) 4.1.B. (Cont'd) 2.
With both RPS electric power 2.
At least once per 18 months monitoring channels for an by demonstrating the OPERA-BILITY of overvoltage, under-inservice RPS MG set or alternate power supply voltage and underfrequency l
inoperable, restore at least protective instrumentation by one to OPERABLE status within simulated automatic logic 30 minutes or remove the actuation and verification of the circuit protector trip associated RPS MG set or alternate power supply level setting as follows.
from service.
(a) overvoltage -
4 132.0 VAC (b) undervoltage i 108.$ VAC (c) underf requency L' 56.011z i
l 1
BFN 3.1/4.1 la Amendment 149 Unit 3
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