ML20196J461
| ML20196J461 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/01/1988 |
| From: | Zech G NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20196J466 | List: |
| References | |
| TAC-00176, TAC-00177, TAC-00178, TAC-176, TAC-177, TAC-178, NUDOCS 8803140336 | |
| Download: ML20196J461 (15) | |
Text
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UNITED STATES 8"
j NUCLEAR flEGULATORY COMMISSION
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING llCENSE Amendment No. 146 License No. OPR-33 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated May 15. 1987 complies with the standards and reouirements of the Atomic Energy Act of 1954. as amended (the Act).
and the Comission's rules and reculations 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 er.dangering the health and safety of the public, and (ii) that such act.ivities 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.
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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.146, are hereby incorporated in the license. The licersee 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 dais from the date of issuance.
FOR THE NUCLEAR REGUI.ATORY COMMISSION
- p N
GarM.Zech, Assn.nt Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Chances to the Technical Specifications Date of issuance: March 1, 1983
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s ATTACHMENT TO LICENSE AMENCMENT NO.146 FACILITY OPERATING LICENSE NO. OPR-33 00CKET 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 captioried amendrwnt number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
.j REMOVE INSERT 3.7/4.7-17 3.7/4.7-17*
3.7/4.7-18 3.7/4.7-18
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3.1/4.7 COWTAINMENT SYSTEMS LIMITIFC CONDITIONS FOR OPERATION SURVRIf.f.ANCE REQUIREMENTS 3.1.C.
If refueling zone secondary containment cannot be maintained the following conditions shall be met:
s.
Handling of spent fuel and all operations over spent fuel pools and open reactor i
wells containing fuel shall be prohibited.
I b.
The standby gas treatment system suction to the refueling zone will be blocked except for a I
contro1*ted leakage area I
sized to assure the achieving of a vacuum of at least 1/4-inch of water and not over 3 inches of water in all three reactor zones.
't D.
Primary Containment Isolation Valves D. Erin 3rr Containment Isolation Valves i
1.
When Primary Containment 1.
The primary containment Integrity is required, all isolation valves isolation valves listed in surveillance shall be Table 3.7.A and all reactor performed as follows:
coolant system instrument line flow check valves a.
At least once per shall be OPERABLE except as operating cycle the specified in 3.7,0.2.
OPERABLE isolation valves that are power operated and automatically initiated shall be tested for simulated automatic initiation and closure
- times, b.
At least once per quarter:
(1) All normally open power-operated i
isolation valves (except for the ~4tn steam line power-operated isolation valves) shall be fully iloved en re Pened.
gry 3.7/4,7 17
o 3.7/a.7 CONTAINNENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.1.D. Primary Containment Isolation 4.7.D.
Primary Containnent Isolation Valves Valves 4.7.D.1.b (Cont'd)
(2)
With the reactor power less than 75%. trip main steam isolation valves individually and verify closure time.
c.
(Deleted)
- d. At least once per operating cycle, the operability of the reactor coolant system instrument line flow check valves shall be verified.
- 2. In the event any isolation valve
- 2. Whenever an isolation valve specified in Table 3.7.A becomes listed in Table 3.7.A is INOPERABLE reactor power IMOPERABLE, the position of at operation may continue provided least one other valve in each at least one valve in each line line having an INOPERABLE valve having an IMOPERABLE valve, is shall be recorded daily.
OPERABLE and withf.n 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either
- a. The IMOPERABLE valve is restored to OPERABLE status, or
- b. Each affected line is isolated by use of at least one deactivated containment isolation valve secured in the isolated position.
- 3. If Specification 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
BFW 3.7/4 7-18 A,endment No. 146 Unit 1
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'o, UNITED STATES NUCLEAR REGULATO3Y COMMISSION 2
l W ASHING TON, D. C, 2MM TENNESSEE VALLEY AUTHORITY DOCKET NO. S0 260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.142 License No. OPR-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated May 15, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act1, and the Comission's rules and regulation; tet 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 (i) that the activities authori:ed by this amendment can be conducted without endancering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission'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 accorcance with 10 CFR Part 51 of the Comission's regulations and all applicable recuirerents have been satisfied.
T 2
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. OPR-52 is hereby r
amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No.142. 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.
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FOR THE NUCLEAR REGULATORY COMMIS$10N O
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M CeL Gar Zech. Assis m t Director for Projects TVA Frojects Division Office of Special Projects
Attachment:
Changes to the Technical i
Specifications Date of Issuance: March 1. 1983 i
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e ATTACHMENT TO LICENSE AMENOMENT NO 142 FACILITY OPERATING LICENSE NO OPR-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 emendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3.7/4.7-17 3.7/4.7-17*
3.7/4.7-18 3.7/4.7-18
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3.7/4.?
CONTAIUMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.?.C.
Secnndarr_Ceniainment 4.
If refueling zone secondary containment cannot be maintained the following conditions shall be mett Handling of spent fuel and l a.
all operations over spent fuel pools and open reactor wells containing fuel shall be prohibited.
b.
The standby gas treatment system suction to the refueling zone will be blocked except for a controlled leakage area j
sized to assure the achieving of a vacuum of at least 1/4-inch of water and not over 3 inches of water in all three reactor I
zones.
l D.
Primary Containment Isolation Yelves D. Egitary Containment Isolation Valves l
1.
When Primary Containment 1.
The primary containment Integrity is required, all isolation valves isolation valves listed in survelliance shall be Table 3.7.A and all reactor performed as follows:
coolant system instrument line flow check valves a.
At least once per shall be OPERABLE except as operating cycle the specified in 3.7.D.2.
OPERABLE isolation valves l
that are power operated
,and automatically initiate 6 shall be tested for simulated automatic initiation and closure times.
b.
At least once per quarters t
j (1) All noe mally open
[
power-operated isolation valves (except for the main steam line power-operated I
isolation valves)
I shall be fully closed and reopened.
ggg 3.1/a.1-17
3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.D. Primary Containment Isolation 4.7.D.
Primary Containment Isolation Valves Valves 4.7.D.l.b (Cont'd)
(2)
With the reactor power less than 75%, trip main steam isolation valves individually and verify closure time, c.
(Deleted)
- d. At least once per operating cycle, the operability of the reactor coolant system instrument line flow check valvec shall be verified.
- 2. In the event any isolation valve
- 2. Whenever an isolation valvo specified in Table 3.7.A becomes listed in Table 3.7.A is INOPERABLE, reactor power IWOPERABLE, the position of at operation may continue provided least one other valve in each at least one valve in each line line having an INOPERABLE valve having an INOPERABLE valve, is shall be recorded daily.
OPERABLE and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
- a. The INOPERABLE valve is restored to OPERABLE status, or
- b. Each affected line is isolated by use of at least one deactivated containment isolation valve secured in the isolated position.
i
- 3. If Specification 3.7.0.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
BFN 3.7/4.1-18 Amendment NO. 142 Unit 2 s
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NUCLEAR REGULATORY COMMISSION 5
j WASHING TON, D. C. 206$5
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TENNESSEE VALLEY AUTH0 PITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendrnent No.117 License No. CPR-68 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated May 15, 1987, complies with the standards and recuirements 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 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, ano (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 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 requirerents have been satisfied.
0 s 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.117, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendrent 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 (W44 {
b
>W-d Gary'G. Zech, Assis t Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of issuance:
March 1, 1938
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ATTACEPENT TO LICENSE AMEN 0 MENT NO. 117 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 ider:tified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3.7/4.7-17 3.7/4.7-17*
3.7/4.7-18 3.7/4.7-18 i
a
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L 4
3.7/4.7 CONTAIKMENT SYSTEMS LIMITING COMDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.C.
If refueling zone secondary containment cannot be maintained the following conditions shall be met:
a.
Handling of spent fuel and all operations over spent fuel pools and open reactor wells containing fuel shall be prohibited.
b.
The standby gas treatment system suction to the refueling zone will be blocked except for a controlled leakage area sized to assure the achieving of a vacuum of at least 1/4-inch of water and not over 3 inches of water in all three reactor zones.
D.
Primary Containment Isolation Valves D. Primary Containment Isolation Valves 1.
When Primary Containment 1.
The primary containment Integrity is required, all isolation valves isolation valves listed in surveillance shall be Table 3.7.A and all reactor performed as follows:
coolant system instrument line flow check valves a.
At least once per shall be OPERABLE except as operating cycle the specified in 3.7.D.2.
OPERABLE isolation valves that are power operated and automatically initiated shall be tested for simulated automatic initiation and closure
- times, b.
At least once per quarter:
(1) All normally open powar-operated isolation valves (except for the main steam line power-operat.ed isolation valves) shall be fully closed gF{ 3 3.7/4.7-17
i 3.7/4.7 CONTAIRMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.D. Primary Containment Isolation 4.7.D.
Primary Containment valves Isolation valves 4.7.D.1.b (Cont'd)
(2)
With the reactor power less than 75%,
trip main steam isolation valves individually and verify closure time.
c.
(Deleted)
- d. At least once per operating cycle, the operability of the reactor coolant system instrument line flow check valves shall be verified.
- 2. In the event any isolation valve
- 2. Whenever an isolation valve specified in Table 3.7.A becomes listed in Table 3.7.A is INOPERABLE, reactor power INOPERABLE, the position of at operation may continue provided least one other valve in each at least one valve in each line lin. having an INOPERABLE valve having an INOPERABLE valve, is shall be recorded daily.
OPERABLE and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
- a. The INOPERABLE valve is restored to OPERABLE status, or
- b. Each affected line is isolated by use of at least one deactivated containment isolation valve secured l
in the isolated position.
- 3. If Specification 3.7.D.1 and 3.7.D.2 cannot be met, an j
orderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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BFN 3.7/4.7-18 Amendment No. 117 Unit 3 l
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