ML20071K529
| ML20071K529 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 07/26/1994 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071K531 | List: |
| References | |
| NUDOCS 9408010074 | |
| Download: ML20071K529 (8) | |
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3 UNITED STATES 3'
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NUCLEAR REGULATORY COMMISSION k..... j#
e WASHINGTON, D.C. 205$5-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE0V0YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 185 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 17, 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; 8.
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.
1 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.
9400010074 940726 PDR ADOCK 05000327 P
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment amended to read as follows:and paragraph 2.C.(2) of Facility Operating Lice (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 185, are hereby incorporated in the license.
the Technical Specifications.The licensee shall operate the facility in accordanc 3.
This license amendment is effective as of its date of issuance, to be implemented within 45 days.
l FOR THE NUCLEAR REGULATORY COMMISSION
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Frederick J. Het/ don, Director Project Directorate 11 4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 26, 1994
'i.
I ATTACHMENT TO LICENSE AMENDMENT NO.1as FACILITY OPERATING LICENSE NO. DPR-77 I
DOCKET N0. 50-327 j
Revise the Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contains a marginal line indicating the area of change.
REMOVE INSERT 2-5 2-5 W
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I l
i 1
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4 TABLE 2.2-1 b
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 8
g FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- l. Manual Reactor Trip Not Applicable Not Applicable z
Q
- 2. Power Range, Neutron Flux Low Setpoint - s 25% of RATED Low Setpoint - s 27.4% of RATED THERMAL POWER THERMAL POWER High Setpoint - s 109% of RATED High Setpoint - s 111.4% of RATED THERMAL POWER THERMAL POWER
- 3. Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with s 6.3% of RATED THERMAL POWER High Positive Rate a time constant 2 2 second with a time constant 2 2 second
- 4. Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with s 6.3% of RATED THERMAL POWER High Negative Rate a time constant 2 2 second with a time constant 2 2 second y
- 5. Intermediate Range, Neutron s 25% of RATED THERMAL POWER s 45.20% of RATED THERMAL POWER l
m Flux 5
5
- 6. Source Range, Neutron Flux s 10 counts per second s 1.45 x 10 counts per second l
- 7. Overtemperature AT See Note 1 See Note 3
- 8. Overpower AT See Note 2 See Note 4
- 9. Pressurizer Pressure--Low 2 1970 psig 2 1964.8 psig
- 10. Pressurizer Pressure--High s 2385 psig s 2390.2 psig g
- 11. Pressurizer Water Level--High 5 92% of instrument span s 92.7% of instrument span E
- 12. Loss of Flow 2 90% of design flow 2 89.4% of design flow
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per loop
- per loop
- i
=
- Design flow is 91,400 gpm per loop.
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UNITED STATES
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i NUCLEAR REGULATORY COMMISSION i
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WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE0VOYAH NUCLEAR PLANT. UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.177 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 17, 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.
l l
J 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-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.177, 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, to be implemented within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION
'<b.h:_y)?s,!,,c_.
Frederick J. Hebdon, 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: July 26, 1994
1 ATTACHMENT TO LICENSE AMENDMENT NO.177 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contains a marginal line indicating the area of change.
REMOVE INSERT 2-5 2-5 I
O
TABLE 2.2-1 b
PEACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 8
g
-FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- l. Manual Reactor Trip Not Applicable Not Applicable E
Q
- 2. Power Range, Neutron Flux Low Setpoint - s 25% of RATED Low Setpoint - s 27.4% of RATED THERMAL POWER THERMAL POWER m
High Setpoint - s 109% of RATED High Setpoint - s 111.4% of THERMAL POWER RATED THERMAL POWER
- 3. Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with s 6.3% of RATED THERMAL POWER High Positive Rate a time constant 2 2 seconds with a time constant 2 2 seconds
- 4. Power Range, Neutron Flux, s 5% of RATED THERMAL POWER with s 6.3% of RATED THERMAL POWER High Negative Rate a time constant 2 2 seconds with a time constant 2 2 seconds
- 5. Intermediate Range, Neutron s 25% of RATED THERMAL POWER s 45.20% of RATED THERMAL POWER l
m m
Flux 5
5
- 6. Source Range, Neutron Flux s 10 counts per second s 1.45 x 10 counts per second l
' 7. Overtemperature AT See Note 1 See Note 3
- 8. Overpower AT See Note 2 See Note 4
- 9. Pressurizer Pressure--Low 2 1970 psig 2 1964.8 psig Eg
- 10. Pressurizer Pressure--High
< 2385 psig s 2390.2 psig 5g
- 11. Pressurizer Water Level--High 5 92% of instrument span s 92.7% of instrument span y
- 12. Loss of Flow 2 90% of design flow per loop
- 2 89.4% of design flow per loop
- s
- Design flow is 91,400 gpm per loop.
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