ML20204G542
| ML20204G542 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/28/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20204G547 | List: |
| References | |
| NUDOCS 8608070320 | |
| Download: ML20204G542 (8) | |
Text
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NUCLEAR REGULATORY COMMISSION g
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TENNESSEE VALLEY AUTHORITY t
DOCKET NO.
50-327 g
SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. DPR-77 1.
The Nuclesr Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) Faci'lity Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated October 22, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the license, as amended, 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, 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 comon defense and security or to the health and safety of the public; and E.
Theissuanceofthisamendmentisinaccordancewith15CFRPart51of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.44are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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L e 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W\\
B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A Attachment" Appendix A Technical Specification Changes Date of Issuance: July 28, 1986
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ATTACHMENT TO LICENSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE N0. DPR-77 DOCK $TNO.50-327 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by Amendment nuper and contains vertical lines indicating the areas of change.
Amended Page 2-5 l
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TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS h
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
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- 1. Manual Reactor Trip Not Applicable Not Applicable z
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- 2. Power Range, Neutron Flux Low Setpoint - 1 25% of RATED Low Setpoint 1 26% of RATED w
THERMAL POWER THERMAL POWER High Setpoint - 1 109% of RATED High Setpoint - < 110% of RATED 1
THERMAL POWER THERMAL POWER l
- 3. Power Range, Neutron Flux,
< 5% of RATED THERMAL POWER with
< 6.3% of RATE 6 THERMAL POWER High Positive Rate i time constant 1 2 seconds with a time constant > 2 seconds I
- 4. Power Range, Neutron Flux,
< 5% of RATED THERMAL POWER with
< 6.3% of RATED THERMAL POWER High Negative Rate i time constant 1 2 seconds with a time constant 1 2 seconds
- 5. Intermediate Range, Neutron 1 25% of RATED THERMAL POWER 5 30% of RATED THERMAL POWER Flux j
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5
- 6. Source Range, Neutron Flux i 105 counts per second 5 1.3 x 10 counts per second
- 7. Overtemperature AT See Note 1 See Note 3
- 8. Overpower AT See Note 2 See Note 3
- 9. Pressurizer Pressure--Low
> 1970 psig
> 1960 psig
- 10. Pressurizer Pressure--High
< 2385 psig i 2395 psig g
-< 92% of instrument span
-< 93% of instrument span
- 11. Pressurizer Water Level--High
- 12. Loss of Flow
> 90% of design flow per loop *
> 89% of design flow per loop
- E,
- Design flow is 91,400 gpm per loop.
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UNITED STATES
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TENNESSEE VALLEY AUTHORITY DOCKET NO.
50-328 l
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SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No. DPR-79 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated October 22, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's ' regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations 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 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A 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 Appendix A, as revised through Amendment No.36are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.
i
. 3.
This license amendment is effective as of its date of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION
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B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A Attachment
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Appendix A Technical Specification Changes Date of Issuance: July 28, 1986 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 36 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by Amendment nuk er and contains vertical lines indicating the areas of change.
l Amended Page 2-5 Y
l l
TABLE 2.2-1 l
M S
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS S
R FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- 1. Manual Reactor Trip Not Applicable Not Applicable 5*
- 2. Power Range, Neutron Flux Low Setpoint 5 25% of RATED Low Setpoint - < 26% of RATED THERMAL POWER THERMAL POWER -
N High Setpoint - < 109% of RATED High Setpoint 5 110% of RATED THERMAL POWER THERMAL POWER
- 3. Power Range, Neutron Flux,
< 5% of RATED THERMAL POWER with
<6.3%ofRATEd'THERMALPOWER High Positive Rate i time constant 1 2 seconds with a time constant 1 2 seconds
- 4. Power Range, Neutron Flux,
< 5% of RATED THERMAL POWER with
< 6.3% of RATED THERMAL POWER High Negative Rate i time. constant 1 2 seconds with a time constant 2 2 seconds m
- 5. Intermediate Range, Neutron 5 25% of RATED THERMAL POWER 5 30% of RATED THERMAL POWER
)
Flux 5
5
- 6. Source Range, Neutron Flux
$ 10 counts per second 5 1.3 x 10 counts per second
- 7. Overtemperature AT See Note 1 See Note 3
- 8. Overpower AT See Note 2 See Note 3 I
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- 9. Pressurizer Pressure--Low 1 1970 psig 1 1960 psig
- 10. Pressurizer Pressure--High 5 2385 psig 5 2395 psig i
p
-< 92% of instrument span
-< 93.0% of instrument span
- 11. Pressurizer Water Level--High k.
- 12. Loss of Flow 1 90% of design flow 1 89% of design flow per loop
- per loop
- 8 5
" Design flow is 91,400 gpm per loop.
-