ML20207F426
| ML20207F426 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/08/1988 |
| From: | Black S NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20151T942 | List: |
| References | |
| TAC-00074, TAC-00075, TAC-00076, TAC-74, TAC-75, TAC-76, NUDOCS 8808180288 | |
| Download: ML20207F426 (15) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION g? -
l WASHINGTON, D. C. 20555
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n' TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.152 License No. DPR-33 1.
The Nuclear Regulatory Conmission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 13, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Conmission'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.
8808180280 880808 DR ADOCK 050 9
. 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 154 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 issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
@G [
u za ne Black, Assist nt Di' tor
' 60 Projects TVA Projects Division Office of,Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 8,1988
ATTACHMENT TO LICENSE AMENDMENT N0.152 FACILITY OPERATING LICENSE NO. DPR-33 DOCKET N0. 50-259 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.
Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3.7/4.7-25 3.7/4.7-25 3.7/4.7-26 3.7/4.7-26*
TABLE 3.7.A PRIMARY CONTAINMENT ISOLATION VALVES Number of Power Maximum Action on
~
Operated Valves Operating Normal Initiating Group Valve Identification Inboard Outboard Time (sec.)
Position S Mnal 1
Main steamline isolation valves (FCV-1-14, -26. -37 & -51; l-15
-27.- 38 & -52) 4 4
3<T<5 0
GC 1
Main steamline drain isolation valves (FCV-1-55 & 1-56) 1 1
15 0
GC 1*
Reactor Water sample line isolation valves 1
1 5
C SC 2
RHRS shutdown cooling supply isolation valves (FCV-74-48 & -47) 1 1
40 C
SC l
2 RHRS - LPCI to reactor (FCV-74-53. -67) 2 40 C
SC 2
Reactor vessel head spray isolation valves (FCV-74-77. -78) 1 1
30 C
SC 2
RHRS flush and drain vent to suppression F
chamber (FCV-74-102. -103. -119 & -120) 4 20 C
SC 2
Suppression Chamber Drain (FCV 75-57. -58) 2 15 0*"
GC 7
2 Drywell equipment drain discharge g
isolation valves (FCV-77-15A, & -15B) 2 15 0
GC 2
Drywell floor drain discharge isolation valves (FCV-77-2A & -28) 2 15 0
GC "These valves isolate only on reactor vessel low low water level (470") and main steam line high radiation of Group 1 isolations.
""These valves are normally open when the pressure suppression head tank is aligned to serve the RHR and CS discharge piping and closed when the condensate head tank is used to serve the RHR and CS discharge piping.
(See Specification 3.5.H) cu R
BFN-Unit 1
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e
TABLE 3.7.A (Continued)
Number of Power Maximum Action on Operated Valves Operating Normal Initiating Group Valve Identification Inboard Outboard Time (sec.)
Position Signal 3
Reactor water cleanup system supply isolaion valves (FCV-69-1, & -2) 1 1
30 0
GC 3
Reactor water cleanup system return isolation valves (FCV-69-12) 1 60 0
GC 4
FCV 73-81 (Bypass around FCV 73-3) 1 10 0
GC 4
HPCIS steamline isolation val (FCV-73-2 & -3) 1 1
20 0
GC 5
RCICS steamline isolation valves (FCV-71-2 & -3) 1 1
15 0
GC 6
Drywell nitrogen purge inlet isolation valves (FCV-76-18) 1 5
C SC 6
Suppression chamber nitrogen purge inlet isolation valves (FCV-76-19) 1 5
C SC b
6 Drywell Main Exhaust isolation p
valves (FCV-64-29 and -30) 2 2.5 C
SC 7
6 Suppression chamber main exhaust y
isolation valves (FCV-64-32 and -33) 2 2.5 C
SC 6
Drywell/ Suppression Chamber purge inlet (FCV-64-17) 1 2.5 C
SC 6
Drywell Atmosphere purge inlet (FCV-64-18) 1 2.5 C
SC BFN-Unit 1 s
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UNITED STATES g
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g NUCLEAR REGULATORY COMMISSION 5.'-
l WASHINGTON, D. C. 20555 8
,o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 RROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.148 License No. DPR-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 13, 1988, complies with the stand'rds 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 conformity with the application, the provisions of the Act, and the rules and regula.tions 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 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 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. DDR-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.148, 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 issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
"@~%
e Black, Assi M Director Su no fbr/ rojects P
TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:' August 8,1988 G
m.
ATTACHMENT TO LICENSE AMENDMENT ?!0:148 FACILITY OPERATING LICENSE NO. DDR-52 DOCKET N0. 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.
Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3.7/4.7-25 3.7/4.7-25 3.7/4.7-26 3.7/4.7-26*
O k
1ABIE 3.7.A PRIMARY CONTAINMLNI ISOLATION VALVES Number of Power Maximum Action on Operated Valves Operating Nonnal Initiating Group Valve Identification Inboard outboard Time (sec.)
Position Signal i
Main steamline isolation valves (FCV-1-14, 26, 37, & Sl; l-15, 21, 38, & S2) 4 4
3<T<S 0
GC 1
Main steamline drain isolation valves (FCV-1-SS & 1-56)
I 1
IS 0
GC la Reactor Water sgle line isolation valves 1
1 5
C SC 2
RilRS shutdown cooling supply isolation valves (FCV-74-48 & 41) 1 I
40 C
SC 2
RilRS - LPCI to reactor (FCV-14-53 & 67) 2 40 C
SC l
2 RilRS flush and drain vent to suppression v
chamber (FCV-74-102,103,119, & 120) 4 20 r-SC Np 2
Suppression Chanber Drain (FCV-75-SI, 58) 2 IS 0**
GC w
ab.
2 Drywell equipment drain discharge m
isola
- ion valves (FCV-17-ISA & 158) 2 15 0
GC 2
Drywell ficor drain discharge isolation valves (FCV-FF -2A & 28) 2 IS 0
GC
- lhase va.lves isolate only on reactor vessel low low water level (410") and main steam line high radiation of
- )t.9 1 isolations.
(See Specification 3.5.11)
BIN Unit 2 a
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TABLE 3.7.A (Continued)
Number of Power Maximum Action on Operated Valves Operating Normal
' Ini tiating Grovo Valve Identification inboard Outboard Time (sec.)
Position Signal 3
Reactor water cleanup system supply isolation valves FCV-69-1. & 2 1
1 30 0
GC 4
FCV 73-81 (8ypass ar e.d FCV 73-3) 1 10 0
GC 4
HPCIS steamline isolation valves FCV-73-2 & 3 1
1 20 0
GC 5
RCICS steamline isolation valves FCV-71-2 & 3 1
1 15 0
GC 6
Drywell nitrogen purge inlet isolation valves (FCV-76-18) 1 5
C SC 6
Suppression chamber nitrogen purge inlet isolation valves (FCV-76-19) 1 5
C SC 6
Drywell Main Exhaust isolation valves (FCV-64-29 and 30) 2 2.5 C
SC
'e 6
Suppression chamber main exhaust
)
isolation valves (FCV-64-32 and 33) 2 2.5 C
SC 7
6 Drywell/Suppresrion Chamber purge w
iniet (FCV-64-1. i 1
2.5 C
SC 6
Drywell Atmosphere purge inlet (FCV-64-18) 1 2.5 C
SC BFN-Unit 2 e
e e
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- p UNITED STATES
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NUCLEAR REGULATORY COMMISSION
/. j WASWNGTON, D. C. 20555 4
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TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-296 BROWNS FERRY NUCLEAR DLANT, UNIT 3 AMENDMENT TO FACILITY ODERATING LICENSE
~,
Amendment No. 123 License No. DDR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 13, 1988, 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 authnrized 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.a 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 Dart 51 of the Commission's regulations and all applicable requirements have been satisfied, 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. DDR-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.123, 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 issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION iredb>r Suz ne Black, Assis t
fo Pfojects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 8, 1988
ATTACHMENT TO LICENSE AMENDMENT N0.123 FACILITY OPERATING LICENSE N0. DDR-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 icantified by' the captioned-amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3.7/4.7-24 3.7/4.7-24 3.7/4.7-25 3.7/4.7-25*
l l
9 g
a 1A8t.E 3.1.A PRIMARY CONTAINMLNI ISOLATION VALVES Number of Power Maximum Action on Operated Valves Operating Nonnal Initiating Grpup Valve identification inboard Outboard Time (sec.)
Position S_ignal 1
Main steamline isolation valves
-27,- 38, & -5E) 31, & -51; l-15 (FCV-1-14, 4 4
3<T<5 0
GC 1
Main steamline drain isolation valves (FCV-1-55 & 1-56) 1 1
15 0
GC I*
Reactor Idater saapie line isolation valves 1
1 5
C SC 2
RitRS shytdown cooling supply isolation valves (FCV-14-48 & -47) 1 1
40 C
SC 2
RitRS - LPCI to reactor (FCV-14-53, -67) 2 40 C
SC l
2 RHRS flush and drain vent to suppression chamber (FCV-14-102, -103, -119, & -120) 4 20 C
SC U
2 Suppression Chamber Drain (FCV 15-57, -58) 2 15 0**
GC A
2 Drywell equipment drain discharge isolation valves (ICV-77-15A, & -ISB) 2 15 0
GC e%
2 Orywell floor drain discharge isolation valves (FCV-FF-2A & -28) 2 15 0
GC
- Ihese ulves isolate only on reactor vessel low low water level (410") and main steam line high radiation of Group 1 isolations.
(See Specification 3.5.11)
BI N -tinit 3 a
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TABLE 3.7.A (Cont'd)
Number of Power Maximum Action on Operated Valves Operating Normal Initiating Group Valve 'Jentification Inboard Outboard Time (sec.)
Posi tion Signal 3
Reactor water cleanup system supply isolation valves (FCV-69-1. & -2) 1 1
30 0
GC 4
FCV-73-81 (Bypass around FCV-73-3) 1 10 0
GC 4
HPCIS steas,line isolation valves (FCV-73-2 & -3) 1 1
20 0
GC 5
RCICS steamline isolation valves (FCV-71-2 & -3) 1 1
15 0
GC 6
Oryweli nitrogen purge inlet isolation valves (FCV-76-18) 1 5
C SC 6
Suppression chas6er nitrogen purge inlet isolation valves (FCV-76-19) 1 5
C SC 6
Drywell Main Exhaust isolation valves (FCV-64-29 and -30) 2 2.5 C
SC 6
Suppression chamber main exhaust isolation valves (FCV-64-32 and -33) 2 2.5 C
SC w
Z 6
Drywell/ Suppression Chamber purge c-inlet (FCV-64-17) 1 2.5 C
SC Y
6 Drywell Atmosphere purge inlet U
(FCV-64-18) 1 2.5 C
SC BFN-11 nit 3 g
G e
.