ML20237G747
| ML20237G747 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/21/1987 |
| From: | Zwolinski J NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20237G751 | List: |
| References | |
| TAC-64314, TAC-64315, TAC-64316, NUDOCS 8709020392 | |
| Download: ML20237G747 (15) | |
Text
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f UNITED STATES f
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'g NUCLEAR REGULATORY COMMISSION 3"
- 1. - l WASHINGTON, D. C. 20555 l
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TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 J
/
AMENDMENT TO FACILITY OPERATING LICENSE i
4 s, j
Amendment Rc 136 s
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 December P3, 1986, compliet with the standards and i
i requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFP.
Chapter I; B,
The facility will operate in conformity wilih the application, the l
provisions of the Act, rnd tr,e rules and regulations of the i
Commission; i'
C.
There is reasonable assurance (i) thit the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will he conducted in compliance with the. Commission's regulations; D.
The issuance of this amendment will not be inimical to the common dpfenseandsecurityortothehea.lthandsafetyofthepublic;and E.
The issuance of this amendment. is in accordance with 10 CFR Part 51 of' the Commission.'s regulation.s and all applicable requirements have been satisfied.
8709020392 870821 l.
PDR ADOCR 05000259l, P
PDR L__.________---_.--.-
1 1
I '
2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment i
and paragraph 2.C.(2) of Facility Operating License No. OPR-33 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through f.mendment No.136 are hereby incorporated in the license. The licensee shall operate the facility in accordance with t.he Technical Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 60 days from the date of isst o ce.
FOR THE NUCLEAR REGULATORY COMMISSION Fer dohn A. 'Zwolinski, Assistant Director for Projects TVA Projects Division Office 4)f Special Projects
Attachment:
' Changes to the Technical Specifications Date of Issuance: August 21, 1987 l
ATTACHMENT TO LICENSE AMENDMENT N0.136 FACILITY OPERATING LICENSE NO. DPR-33 l
DOCKET NO. 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.
]
l REMOVE INSERT 3.4/4.4-1 3.4/4.4-1 3.4/4.4-2 3.4/4.4-2 i
l l
l 1
3.4/4.4 STANDBY LIQUID CONTROL SYSTEM l
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM Applicability Applicability Applies to the operating status Applies to the surveillance of the Standby Liquid Control requirements of the Standby System.
Liquid Control System.
Obj ective Objective To assure the availability of a To verify the operability of the system with the capability to Standby Liquid Control System.
shut down the reactor and maintain the shutdown condition without the use of control rods.
Specification Specification A.
Normal System Availability A.
Normal System Availability 1.
The Standby Liquid Control The operability of the Standby System shall be operable Liquid Control System shall be at all times when there verified by the performance is fuel in the reactor of the following tests:
vessel and the reactor is not in a shutdown condition 1.
At least once per month with all operable control each pump loop shall be rods fully inserted except functionally tested.
as specified in 3.4.B.1.
l 2.
At least once during each operating cycle:
a.
Check that the setting of the system relief valves is 1,425 1 7 ',
psig.
1 b.
Manually initiate the system, except explo-sive valves. Visually verify flow by pumping j
boron solution through j
the recirculation path i
and back to the Standby l
Liquid Control Solution l
Tank. Verify minimum I
pump flow rate of 39 gpm against a system
]
. head of 1275 psig by j
pumping demineralized water through the BFN 3.4/4.4-1 Unit 1 AMENDMENT NO. 136 i
u_-____
4 3.4/4.4 STANDBY LIQUID CONTROL SYSTEM d
l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.4.A Normal System Applicability 4.4.A.2.b. (Cont'd)
Standby Liquid Control Test Tank. After pumping boron solution, the system shall be flushed with demineralized water.
- c. Manually initiate one of the Standby Liquid Control System loops and pump demineralized water into the reactor vessel.
This test checks explosion of the charge associated with the tested loop, proper operation of the valves, and pump operability.
Replacement charges shall be selected such that the age of charge in service shall not exceed five years from the manufacturer's assembly date.
d.
Both systems, including both explosive valves, shall be tested in the course of two operating cycles.
B.
Operation with Inoperable B.
Surveillance with Inoperable 1
Components Components 1.
From and after the date 1.
When a component is found that a redundant component to be inoperable, its is made or found to be redundant component shall inoperable, Specification be demonstrated to be 3.4.A.1 shall be considered operable immediately and fulfilled and continued daily thereafter until the operation permitted inoperable component is provided that the
- repaired, component is returned to an operable condition within'seven days'.
Unit 1 l
AMEMDMENT NO,136 4
c8 UNITED STATES i
NUCLEAR REGULATORY COMMISSION j
., ASHING TON, D. C. 20555 1
TENT!ESSEE VALLEY AUTH0 PITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPEPATING LICENSE 1
Amendment No.132 License No. DPP-5?
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensec) dated Decerber 23, 1986, complies with the standards ard requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commissior,'s rul u 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 1
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; 0.
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 i
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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.132, 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 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J".
~~ Q -
r.
hohnA.Zwolinski,AssistantDirector for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 21, 1987
l ATTACl MENT TO LICENSE AMENDMENT N0.132 l
FACILITY OPERATING LICENSE NO. DDR-52
{
DOCKET N0. 50-260 Revise the Appendix A Technical Specifications by removina the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal I
lines indicating the area of change.
REMOVE INSERT l
3.4/4.4-1 3.4/4.4-1 1
3.4/4.4-2 3.4/4.4-2 l
l l
l
1 J
3.4/4.4 STANDBY LIQUID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM Applicability Applicability Applies to the operating status Applies to the surveillance of the Standby Liquid Control requirements of the Standby
(
System.
Liquid Control System.
l Obj ective Objective To assure the availability of a To verify the operability of the system with the capability to Standby Liquid Control System, shut down the reactor and maintain the shutdown condition without the use of control rods.
Specification Specification A.
Normal System Availability A.
Normal System Availability 1.
The Standby Liquid Control The operability of the Standby System shall be OPERABLE Liquid Control System shall be at all times when there verified by the performance is fuel.'n the reactor of the following tests:
vessel and the reactor is not in a shutdown condition 1.
At least once per month with all OPERABLE control each pump loop shall be rods fully inserted except functionally tested.
as specified in 3.4.B.1.
2.
At least once during each operating cycle:
a.
Check that the setting of the system relief valves is 1,425 1-75
)
psig.
b.
Manually initiate the system, except explo-sive valves.
Visually verify flow by pumping boron solution through the recirculation path and back to the Standby Liquid Control Solution Tank, 'erify minimum flow rate of 39 gpm against a system head of 1275 psig by pumping demineralized "j
water throagh the 3.4/4.4-1 g
AMENDMENT N0, 132
)
-__ _ - _ O
3.4/4.4 STANDBY LIQUID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.4.A Normal System Applicability 4.4.A.2.b. (Cont'd)
Standby Liquid Control Test Tsak. After pumping boron solution, the system shall be flushed with demineralized water,
- c. Manually initiate one of the Standby Liquid Control System loops and pump demineralized water into the reactor vessel.
This test checks explosion of the charge associated with the tested loop, proper operation of the valves, and pump operability.
Replacement charges shall be selected such that the age of charge in service shall not exceed five years from the manufacturer's assembly date.
d.
Both systems, including both explosive valves, shall be tested in the 1
course of two operating cycles.
B.
Operation with INOPERABLE B.
Surveillance with INOPERABLE
{
Components Components 1.
From and after the date 1.
When a compone t is found that a redundant component to be INOPERABLE, its is made or found to be redundant component shall INOPERABLE, Specification be demonstrated to be 3.4.A.1 shall be considered OPERABLE immediately and fulfilled and continued daily thereafter until the operation permitted INOPERABLE component is provided that the repaired.
component is returned to an OPERABLE condition within seven days.
BFW 3.4/4.4-2 Unit 2 I
AMEN 0 MENT NO. 132
+?p nouq(g UNITED STATES E
p, NUCLEAR REGULATORY COMMISSION 73
'1 l WASHINGTON, D. C. 20555
%, *,.. 4l TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMEiiT 1. FACILITY OPERATING LICENSE Amendment No. 107 License No. DPR-68 1.
The Nuclear Regulatory Conmission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 23, 1986, complies with the standards end requirements of the Atomic Eneray Act of 1954, as amended (the Act),
end 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 l
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.
1
2.
.Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment I
and paragraph 2.C.(2) of Facility Operating License No. DPR-68 is hereby I
amended to read as follows 1
(2) Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.107, 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 l
be implemented within 60 days from the date of issuance.
1 FOR THE NUCLEAR REGULATORY COMMISSION I
S.
Fee John A. Zwolinski, Assistant Director for Projects TVA Projects Division Office of Special Projects 1
I Attachment-Changes to the Technical Specifications Date of Issuance: August 21, 1987 l
ATTACHMENT TO LICENSE AMENDMENT NO. 107 l
FACILITY OPERATING LICENSE NO. DPR-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 3.4/4.4-1 3.4/4.4-1 3.4/4.4-2 3.4/4.4-2 1
J i
i
1 3.4/4.4 STANDBY LIQUID CONTROL SYSTEM J
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM Applicability Applicability
]
Applies to the operating stscus Applies to the surveillance of the Standby Liquid Control requirements of the Standby System.
Liquid Control System.
Objective Objective To assure the availability of a To verify the operability of the cystem with the capability to Standby Liquid Control System.
shut down the reactor and maintain the Shutdown Condition without the use of control rods.
Specification Specification A.
Normal System Availability A.
Normal System Availability 1.
The Standby Liquid Contro?
The operability of the Standby System shall be OPERABLE Liquid Control System snall be at all times when there verified by the performance is fuel in the reactor of the following tests:
vessel and the reactor is not in a Shutdown Condition 1.
At least once per month with all OPERABLE control each pump loop shall be rods fully inserted except functionally tested.
as specified in 3.4.B.1.
4 2.
At least once during each operating cycle:
a.
Caeck that the setting of the system relief valves is 1,425 i 75 psig.
b.
Manually initiate the l
system, except explo-valves. Visually verify flow by pumping boron solution through che recirculation path and back to the Standby Liquid Control Solution Tank. Verify minimum pump flow rate of 39 spm against a system head of 1275 psig by i
pumping demineralized wate.r through the BFN-Unit 3 3.4/4 4-1 AMENDMENT NO. 107
3.4/4.4 STANDBY LIQUID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.4.A Normal System Applicability Standby Liquid Control Test Tank. After pumping boron solution, the system shall be flushed with dimeralized water.
c.
Manually initiate one of the Standby Liquid Control System loops and pump demineralized water into the reactor vessel.
This test checks explosion of the charge associated with the tested loop, proper operation of the valves, and pump operability.
Replacement charges shall be selected such that the age of charge in service shall not exceed five years from the manufacturer's assembly date.
d.
Both systems, including both explosive valves, shall be tested in the course of two operating cycles.
B.
Operation with Inoperable B.
Survellicnce with Inoperable Components Components 1.
From and after the date 1.
When a component is found that a radundant component to be INOPERABLE, its is made or found to be redundant component shall INOPERABLE, Specification be demonstrated to be 3.4.A.1 shall be considered OPERABLE immediately ano fulfilled and continued daily thereafter until the operation permitted INOPERABLE component is provided that the repaired.
component is returned to an OPERABLE condition within seven dnys.
BFN-Unit 3 3.4/4.4-2 AMENDMENT NO. 107