ML18038B171
| ML18038B171 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/02/1995 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18038B172 | List: |
| References | |
| DPR-33-A-218, DPR-52-A-234, DPR-68-A-192 NUDOCS 9503070375 | |
| Download: ML18038B171 (19) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT I
~.
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
218 License No.
DPR-33 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority. (the licensee) dated September 30,
- 1993, 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.
9503070375 950302 PDR ADOCK 05000259 I
P PDR
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:
3.
(2)
Technical S ecifications The Technicil Specifications contained in Appendices A and 8, as revised through Amendment No. 218, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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 COMMISSION
/Dx Project Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 2, 1995
ATTACHMENT TO LICENSE AMENDMENT NO.
2 8 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.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Overleaf page is provided to maintain document completeness.
REMOVE 3.10/4.10-7 3.10/4.10-8 INSERT 3.10/4.10-7 3.10/4.10-8*
S v
4 CO
'0 0
S I
G COHDITIO S FOR OPE ION 3.10.C S
e t Fuel Pool Wate SURVEILLANCE RE UIREME S
4.10.C S ent Fue Pool Water Whenever irradiated fuel is stored in the spent fuel pool, the pool water level shall be maintained at a
depth of '8-1/2 feet or greater above the top of the spent fuel.
,A -minimum of 6-1/2 feet of water shall be maintained over single irradiated fuel assemblies during transfer and handling operations.
Whenever irradiated fuel is stored in the spent fuel pool, the water level shall be verified to be above the low level alarm setpoint or the water level shall be measured.
This action shall be taken daily and recorded.
2 ~
Whenever irradiated fuel i' in the fuel pool, the pool water temperature shall be g150'.
2.
Whenever irradiated'uel is stored in the spent fuel pool, the temperature shall be measured and recorded daily.
3.
Fuel pool water, shall be maintained within the following limits:
conductivity g 10 thos/cm at 25 C.
3.
A sample of fuel pool water shall be analyzed for conductivity and chloride content:
a.
Daily, or chlorides g 0.5 ppm b.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the fuel pool cleanup system is inoperable.
BFH Unit 1 3.10/4.10-7 AIfENDHENT NO. 218
1 4
CORE ALTERATIONS LIMITING CONDITIONS FOR OPERATION SURVEILLA CE RE UI EMENTS 3.10.D Reactor Buildin Crane 4.10.D Reactor Buildin Crane 1.
The reactor building crane shall be OPERABLE:
The following operational checks and inspections shall be performed on the reactor building crane prior to handling of a
.spent fuel cask and new or spent fuel.
(These need not be performed more frequently than quarterly.):
a.
When a spent fuel cask is handled.
a.
The cab and pendant controls shall be demonstrated to be OPERABLE on both the 125-'ton hoist and the 5-ton hoist.
b.
Whenever new or spent fuel is handled with the 5-ton hoist.
b.
A visual inspection shall be made to insure structural integrity of, the 125-ton hoist, the 5-ton hoist and cask yoke safety wire ropes.
C ~
The overtravel limit switch interlocks, movement speed control and braking operations for the bridge, trolley and
- hoists, the pendant BFN Unit 1 3.10/4.10-8
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++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 T NNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROMNS FERRY NUCLEAR PLANT UNIT 2
~
AMENDMENT TO FACILITY OPERATING L'ICENS Amendment No. 234 License No. DPR-52 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 30,
- 1993, 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:
3.
(2)
Technical S eci ficati ons The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 234',
are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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 COMMISSION Frederick J.
Heb on, Director Project Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
1'faxch 2, 1995
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise the Appendix A Techni al 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 page is provided to maintain document completeness.
REMOVE 3.10/4.10-7 3.10/4.10-8
~INS RT 3.10/4.10-7 3.10/4.10-8*
4 1
CORE ALTERATIONS "I'
G CO ITIO S FOR OPE IO SURVEILLANCE RE UIREME S
3.10.C S ent Fuel Pool Wate 4'.10.C S ent Fuel Pool'ater Whenever irradiated fuel is stored in the spent fuel pool, the pool water level shall be maintained at a depth of 8-1/2 feet or greater above the.top of the spent fuel.
A minimum of 6-1/2 feet. of water shall be maintained over single irradiated fuel'ssemblies.
during transfer
'nd handling operations.
Whenever irradiated fuel is stored in the spent fuel pool, the water level shall be verified to be above the 1'ow level alarm
.setpoint or the water level shall be measured.
This action shall be taken daily and recorded.
2 ~
Whenever irradiated fuel is in the fuel pool, the pool water temperature shall be S150 F.
2.
Whenever irradiated fuel is stored in the spent fuel pool, the temperature shall be measured and recorded daily.
3.
- Fuel pool water shall be maintained within the following limits:
conductivity g 10 pmhos/cm at 25'C 3.
A sample of fuel pool water shall be analyzed for conductivity and chloride content:
a.
Daily, or chlorides S 0.5 ppm b.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the fuel pool cleanup system is inoperable.
BFH Unit 2 3.10/4.10-7 AMEND?lENT N0.234
1 4
1 CORE ALTERA 0
S
'7'IMITING CONDITIO S FOR OPERATIO SURVEILLANCE RE UIREMENTS 3.10.D Reactor Buildi Crane 4.10.D Reactor Build n Crane 1.
The reactor building crane shall be OPERABLE:
The following operational checks and inspections shall be performed on the reactor building crane prior to handling of a spent fuel cask and new or spent fuel.
(These need not be performed more frequently than quarterly.):
a.
When a spent fuel cask is handled.
a.
The cab and pendant controls shall be demonstrated to be OPERABLE on both the 125-ton hoist and the 5-ton hoist.
b.
Whenever
.new or spent fuel is handled with the 5-ton hoist.
b.
A visual inspection shall be made to insure structural integrity of the 125-ton hoist, the 5-ton hoist and cask yoke safety'ire ropes.
C ~
The overtravel limit switch interlocks, movement speed control and braking operations for the bridge, trolley and
- hoists, the pendant
'BFN Unit 2 3'.10/4.10-8
~
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'0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR.PLANT UNIT 3
~
AM NDMENT TO FACILITY OPERATING LICENSE Amendment No. 192 License No. DPR-68 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September
.30,
- 1993, 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 th'is 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:
3.
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 192.,
are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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 COMMISSION Frederick J.
Heb n, Director Project Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
Narch 2, 1995
ATTACHMENT TO 'LICENSE AMENDMENT NO. 1
~
FACILITY OPERATING LICENSE NO.
DPR-68 DOCKET NO. 50-296 r
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 page is provided to maintain document completeness.
'REMOVE 3.10/4.10-7 3.10/4.10-8 INSERT 3.10/4.10-7 3.10/4.10-8*
0 4
CORE ERATIO S
CO ITIONS FOR OPE IO SU VE LLA CE RE UIREME S
3.10.C S ent Fuel Pool Water 4.10.C S ent Fuel Pool Water Whenever, irradiated fuel is stored in the spent fuel pool, the pool water level shall be maintained at a depth of 8-1/2 feet or greater above the top of the spegt fuel.
A minimum of 6-1/2 feet of water shall be maintained over single irradiated fuel assemblies during transfer and handling operations.
Whenever irradiated fuel is stored in the spent fuel pool, the water level shall be verified to be above the. low level alarm setpoint or the water level shall be measured.
This action shall be 'taken daily and recorded.
2 ~
Whenever irradiated fuel is in the fuel, pool, the pool water temperature shall be gl50 F.
2.
Whenever irradiated fuel is stored in the spent fuel pool, the temperature shall be measured and recorded daily.
3.
Fuel pool water shall be maintained within the following limits:
conductivity g 10 pmhos/cm at 25'C 3.
A. sample of fuel pool water shall be analyzed for conductivity and chloride content:
a.
Daily, or chlorides S 0.5 ppm b.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the fuel pool cleanup system is inoperable.
BFH Unit 3 3.10/4.10-7 AIIZNDTIENT NO. 192
Il II
1 /4 1
CORE ALTERATIONS LIMITING CONDITIONS FOR OPERATION 3.10.D Reactor Buildin Crane 4.10.D Reactor Bu ldi Gran SURVEILLANCE RE UIREMENTS l.
The reactor building crane shall be OPERABLE:
The following operational checks and inspections shall be performed on the reactor building crane prior to handling of a spent fuel cask and new or spent fuel.
(These need not be performed more frequently than quarterly.):
a.
When a spent fuel cask is handled.
a.
The cab and pendant controls shall be demonstrated to be OPERABLE on both the 125-ton hoist and the 5-ton hoist.
b.
Whenever new or spent fuel is handled with the 5-ton hoist.
b.
A visual inspection shall be made to insure structural integrity of the 125-ton hoist, the 5-ton hoist and cask yoke safety wire ropes.
c ~
The overtravel limit switch interlocks, movement speed control and braking operations for the bridge, trolley. and
- hoists, the pendant interlocks, the main-auxiliary hoist operation interlock, and the remote emergency stop shall be functionally tested.
BFN Unit '3 3.10/4.10-8
0 II.
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4 R,