ML20148E313
| ML20148E313 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/19/1988 |
| From: | Zech G NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20148E317 | List: |
| References | |
| TAC-R00031, TAC-R00032, TAC-R00033, TAC-R31, TAC-R32, TAC-R33, NUDOCS 8801260005 | |
| Download: ML20148E313 (15) | |
Text
/js,a aseg'C, UNITED STATES E 7. e
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NUCLEAR REGULATORY COMMISSION g
l W ASmNGTON, D. C. 20555
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TfNNESSEE VALLEY AUTHORITY DOCKET N0. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amerdtrent No.140 License No. OPR-33 1.
The Nuclear Regulatory Comissioi) (the Commission) has found that:
A.
The application for amendment by Tenressee Valley Authority (the licensee) dated May 29, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in ccnformity with the application, the provisions of the Act. and '.he rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amerdr'.ent 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 ccmon defense and security or to the health and safety of the public; and E.
The issuance of this acendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements bate been satisfied.
i 8801260005 880119 DR ADOCK O 29
.i
,' 2.
Accordingly, the license is amended by charges to the Technical Specifications as indicated in the attachtrent to this license amendrent 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 contaitied in Appendices A and B, as revised through Aniendment No.140, 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 date of inscance and shall be implemented within 60 days from the date of issuance.
FOR TriE NUCLEAR REGULATORY COMMISSICN-X Gary G. Zech, As dstant Director for Projects TVA Projects Division Office of Special Projects Attachnient:
Changes to the Technical Specifications Cate of Issuance: January 19, 1988 1
I 1
l j
ATTACEMENT TO LICENSE AMEl4DMEFT NO.140 i
FACILITY OPFRATING LICENSE NO. DPR-33 LOCKET NO. E0-259 Revise the Appendix A Techrical Specifications by removing the pages 163ntified below and inserting the enclosed pages. The revised pages are identified by the captiened amendment number and contain narginal lines indicating the area of change. 0verleaf page* is provided to maintain document completeness.
REMCVE INSERT 3.2/4.2-9 3.2/4.2-9 3.2/4.2-10 3.?/4.2-10*
1 4
TABLE 3.2.A (Continued)
PRIMARY CONTAINMENI AND reactor BUllDING 150LAll0N INSTRUMENIAlloN 9?
Ministen No.
Ins trisnent Channels Operable perTripSys(l)(II) function Trip tevel Setting Action (1)
Rem p s 1
Instrument Channel -
-< 100 mr/hr or downscale f
1.
I upscale or 2 downscale will Reactor Building a.
Initiate SGIS Ventilation High b.
Isolate refueling floor Radiation - Refueling lone c.
Close atmosphere control systm.
2(7) (8)
Instrument Channel
->2000 cfm and < 4000 cfm H and Below 2000 cfm airflow R.ll.
SGIS Flow - Train A (A or F) heaters shall be shut off.
R. H. Heaters l
2(7) (8)
Instrument Channel
>2000 cfm and < 4000 clu H and Below 2000 cfm airflow R.ll.
SGTS Flow - Train B
~
~
(A or I) heaters shall be shut off.
R. H. Heaters 2(7) (8)
Instrument channel
>2000 cfm and 5 4000 cfm H and Below 2000 cfm airflow R.H SGIS flow - Train C (A or I) heaters shall be shut off.
w R. H. Heaters s
- ~
I licactor Building Isolation 0 $ t 5 2 secs.
H or I 1.
Below trip setting prevents w
e Timer (refueling floor) spurious trips and systm perturbations from initiating isolation.
1 Reactor Building Isolation 0 $ t $ 2 secs.
G or A 1.
Below trip setting prevents ilmer (reactor Zone) or H spurious trips and system perturbations from initiating isolation.
2(10)
Group 1 (Initiating) Logic N/A A
1.
Refer to Table 3.l.A for list of valves.
BIN Unit 1 3>
a ir!
3 O
't
~
TABLE 3.2.A (Continued)
PRIMARY CONTAINMENI AND REACTOR BUILDING 150LAil0N INSTRUMENTAIION E 9,,
Miniman No.
Instrisment Channels Operable per Trip Sys(l)(II)
Function Trip level Setting Action (1)
Remarks 1
Group I (Actuation) Logic N/A B
1.
Refer to lable 3.7.A for list of valves.
2 Group 2 (Initiating) Logic N/A A or 1.
Refer to Table 3.7.A for list (8 and E) valves.
1 Group 2 (RHR is91ation-N/A D
Actuation) Logic 1
Group 8 (TIP-Actuation)
N/A J
Logic I
Group 2 (Drywell Supp N/A K
Drains-Actuation) Logic 1
Group 2 (Reactor Building N/A F and G 1.
Part of Group 6 togic
,u
& Refueling Floor, and Drywell Vent and Purge-w)
Actuation) Logic 2
Group 3 (Initiatiruj) Logic N/A C
1.
Refer to Table 3.7.A. for list of valves.
o I
Group 3 (Actuation) Logic N/A C
1 Group 6 Logic N/A F and G 1.
Refer to Table 3.7.A for list of valves.
I Group 8 (Initiating) Logic N/A J
I.
Refer to Table 3.1.A for list of valves.
2.
Same as Group 2 initiating logic.
'N. Unit I
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UNITED STATES I ',
({
NUCLEAR AEGULATORY COMMISSION C
Y. ASHINGTON. D. C. 20555
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TENNESSEE VALLEY AUTHORITY COCKET N0. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENCPENT TO FACILITY OPERATING LICENSE Amendment No.136 License No. OPR-5F 1.
The huclear Regulatory Comission (the Comission) has found that:
A.
The application for amendnent by Tennessee Valley Authority (the licensee) dated May 29, 1987, ecmplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comissior's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions n' the Act, and the rules and rigulations of the Comission; C.
There is reasonable assurance (i) that the activities authori:ed by this amendment can be cor. ducted without endangering the health and eafety of the public, anc (ii) that such activities will be conducted in compliance with the Conmission'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 Comission's regulations and all applicable reouirements have been satisfied.
?.
Accordingly, the licer.se is amended by changer to the Technical Specifications as indicated in the attachmcr.t to this license amendrent and paragraph 2.C.(2) of Facility Operating License No. DPR-52 is hereby arenced to read as follows:
(2) Technical Specifications The Technical Specifications contained in Apperdices A and B, as revised through Amendment No.136, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license atendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLbR REGULATORY COMMISSION Y.
Gary G. -Zech, Assistant Director for Projects TVA Projects Division Office of Special Projects Attactcent:
Charges to the Technical l
Specifications Date of Issuance: January 19, 1988 i
ATTACPPENT TO LICENSE AMENCMENT NO.136 FACILITY OPERATING LICENSE NO. OPR-52 DOCLET FO. 50-200 Revise the Appendix A Technical Specifications by reacving the pages identified belcw and inserting the enclosed pages. The revised rages are identified by the captier.ed amendment _ number ard contain marginal lines inoicating the area of change. Overleaf page* is provided to naintain dccument completeness.
REMOVE INSERT 4
3.2/4.2-9 3.2/4.2-9 3.2/4.2-10 3.2/4.2-10*
i
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TABIE 3.2.A (Continued)
PRIMARY CONIAINMf NI AND RtACIOR BUIIDING 15oLA110N INSIRUNINIAll0N c-co Minimum No.
- 3. {'
Instrument c)
Channels Operable per Trip Sys(l)(ll) function Trip level Setting
_ Action (1)_
,,Rmir k s _,_
m l
Instrument Channel -
< 100 mr/hr or downscale I
1.
I upsrate or 2 downscale will Reactor Building a.
Initiate SGIS Ventilation High b.
Isolate tcf ueling f lenr.
Radiation - Refueling Zone c.
Close almn'.phere (nntent systm.
2(7) (8)
Instrument Channel
>2000 cfm and < 4000 cfm H'and Below 2000 cfm airflow R.li.
SGIS Flow - Train A
~
(A or I) heaters shall be shut off.
R. H. Heaters 2(F) (8)
Instrument Channel
??000 cfm and < 4000 cfm H and Below 2000 cfm airflow R.fl.
SGIS F low - Irain B
( A or I) heaters shall be shut of f.
R. H. Heaters Y
t' 2(F) (8)
Instrument Channel
??000 cfm and < 4000 cfm H and Below 2000 cfm airflow R.II.
SGIS F low - Train C (A or f) heaters shall be shut off.
R. H. Heaters y
ic 1
Reactor Buildi isolation 0 < t < 2 secs.
H or F 1.
Below trip setting preven M Timer (refueli floor) spurious trips and systm perturbations from initiating isolation.
I Reactor Building Isolation 0 < t < 2 secs.
G or A 1.
Below trip setting prevents Timer (reactor zone) or H spurious trips and systm perturbations from initiating isolation.
2(10)
Group I (Initiating) togic N/A A
1.
Refer to lahic 3.J.A for list of valves.
BfN Unit 2
=
'l 3
O m
._m-1A3tt 3.2.A (Continued)
PRIMARY CONIAINMENI AND FJACIOR ".,llllDING ISG;AIION INSIRUMI:41 Alt 0N c~ C3 Minimum No.
1 $'l Instrument Channels Operable N
Per Trip Sys(l)(II)
Function 1 rip level Setting Action (1)_
_ _Remiiks _ _
I Group 1 (Actuation) togic N/A 8
1.
Refer to lah'c 3.7.A for list of valves.
2 Group 2 (Initiating) togic N/A A or 1.
Refer to I.=ble 3.F.A for list (8 and El valves.
1 Group 2 (RilR lsolation-N/A D
Actuation) Logic 1
Group 8 (Tip-Actuation)
N/A J
logic I
Group 2 (Drywell Sung N/A K
Drains-Actuation) logic ta I
Group 2 (Reactor Building N/A I and G I.
Part of Geonp 6 legic g
& Refueling Floor, and s,"
Drywell Vent and Purge-Actuation) togic w
e o
2 Group 3 (Initiating) Logic N/A C
1.
Fef er to Table 3.7. A. f e.-
~
list of valves.
I Group 3 (Actuation) l'ogic N/A C
I Group 6 Logic N/A F and G l.
Refer to Tabic 3.1.A f...
list of valves.
I Group 8 (Initiating) logic N/A J
l.
Refer to I.shic 1.1. A fe**
lid of v.ilves.
7.
s.n as r.,nop 7 initiasim logir.
BfN Unit 2 i
a h
4 i
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4g UNITED STATES
?N NUCLEAR REGULATORY COMMISSION j.1 i
W ASm NG TON, 0, C. 2055$
$ \\,
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....+
TD:NESSEE VALLEY AUTHORITY COLKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.111 License No. OPR-68 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated May 29, 1987, 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 vill operate in confornity with the application, the provisions of the Act, and the rules and rcgulations of the Conmission; 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, ard (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 eil applicable requirements have been satisfied.
1
2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the att6cFrent to this license amendment and paragraph 2.C.(21 cf Facility Operating License No. CFR-68 is hereby an. ended to read as follows:
(0) Technical Specifications The Technical Specifications centained in Aprendices A and B, as-revised through Amendment No.111. are hereby incorporated in the license.
The licensee shall operate the facility in accordence with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance-and shall' be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~
. mG-
,A R > iy.} 'i w Gary G."Zech, Aslistant Director for Projects TVA Projects Division Office cf Special Projects l
Attachmer.t:
Changes to the Technical Specifications Date of Issuance: January 19, 1988 i
l i
I i
1
+r-
ATTACHMENT TO LICENSE AF.ENCMENT tl0.111 FACILITY OPERATING LICENSE N0. DPR-68 00CVET N0. 50-296 Revise tbc Appendix A Technical Specifications by rerreving the pages ider.tified below and inserting the enclosed pages.
The revised pages are identified by the captioned crendment number and centain marginal lines indicating the area of change.
Overleaf pagc+ is provided to maintain docenent completeness.
REMOVE INSERT 3.2/4.2-9 3.2/4.2-9 3.2/4.2-10 3.2/4.2-10*
.t 1
l i
TABIE 3.2.A (Continued)
PRIMARY CONIAINMLNI AND REACTOR BUILDING 150 tall 0N IN51RUMENIAll0N pq Hinimun No.
Instrument Channels Operable per Trip Sys(l)(11)
Function Trip level Setting Action (1)
Remarks w
1 Instrument Channel -
< 100 mr/hr or downscale I
1.
I upscale or 2 downscale will Reactor Building a.
Initiate $Gis b.
Isolate refueling floor.
Ventilation High c.
Close atmosphere control Radiation - Refueling lone system.
I 2(7) (8)
Instrument Channel
? J cfm and 5 4000 cfm H and Celow 2000 cfm airflow R.!!.
(A or f) heaters shall be shut off.
SGIS Flow - Train A R. H. Heaters 2(7) (8)
Instrument Channel 12000 cfm and 1 4000 cfm H and Below 2000 cfm airflow R.H.
(A or F) heaters shall be shut off.
SGIS Flow - Train B R. H. Heaters 2(1) (8)
Instrument Channel 22000 cfm and 5 4000 cfm H and Below 2000 cfm airflow R.lf.
( A or F )
heaters sha11 be shut off.
SGIS Flow - Train C R. H. Heaters w
H or F I.
Below trip setting prevents 1
Reactor Building Isolation 0 $ t $ 2 secs.
spurious trips and systnn Timer (refueling floor) perturbations from to 8
initiating isolation.
G or A 1.
Below trip setting prevents I
Reactor Building Isolation 0 $ t $ 2 secs.
spurious inips and systen or H Timer (reactor zone) perturbations from initiating isolation.
2(IO)
Group 1 (Initiating) Logic N/A A
1.
Refer to Table 3.J.A for list of valves.
BFN Unit 3 pa
'l n
?
i C
TABLE 3.2.A (Continued)
PRIMARY CONIAINMENT AND REACIOR BullDING ISOLATION INSTRUMLNIAllCN gQ Miniesi No.
Insti enent Channels Operable per Trip Sys(I)(II)
Function
_ Trip tevel settinq
_ A: tion (1)
Remarks w
1 Group 1 (Actuation) Logic N/A B
1.
Refer to lable 3.7.A for list of valves.
2 Group 2 (Initiating) togic N/A A or 1.
Refer to Table 3.7.A for list (8 and E) of valves.
I Group 2 (RHR lsolation-N/A D
Actuation) Logic I
Group 8 (11P-Actuation)
N/A J
Logic I
Group 2 (Drywell Simp N/A K
Drains-Actuation) Logic I
Group 2 (Reactor Building N/A F and G l.
Part of Group 6 togic
& Refueling Floor, and Drywell Vent and Purge-u Actuation) Logic g
s 2
Group 3 (Initiating) togic N/A C
I.
Refer to Table 3.7.A. for list of valves.
w I
G 1
Group 3 (Actuation) Logic N/A C
1 Group 6 Logic N/A F and G 1.
Refer to lable 3.7.A for list of valves.
I Group 8 (Initiating) Logic N/A J
1.
Refer to Table 3.7.A for list of valves.
2.
Same as Group 2 initiating logic.
BIN-tinit 3
. ~
.