ML082401446
| ML082401446 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/29/2008 |
| From: | Plant Licensing Branch II |
| To: | |
| Orf, Tracy J.; NRR/DORL 415-2788 | |
| Shared Package | |
| ML082401330 | List: |
| References | |
| TAC MD9501, TAC MD9525 | |
| Download: ML082401446 (4) | |
Text
(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis, instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the Sequoyah and Watts Bar Unit 1 Nuclear Plants.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 319 are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:
- a. Elimination of any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;
- b. Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;
- c. Performance of any test at power level different from there described; and Facility Operating License No. DPR-77 Amendment No. 319
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL NO. MINIMUM OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION
- e. Loss of Power Start
- 1. Voltage Sensors 3/shutdown 2/shutdown 3/shutdown 1,2,3 35 board** board**" -board"
- 2. Load Shed Timer 2/shutdown 1/shutdown 1/shutdown 1,2,3 35 board** board** board**
- f. Trip of Main Feedwater Pumps Start Motor-.
Driven Pumps and..
Turbine Driven Pump 1/pump 1/pump 1/pump(a) 1, 2 (b) 20
- g. Auxiliary Feedwater Suction Pressure-Low 3/pump 2/pump 3/pump 1,2,3 21
- h. Auxiliary Feedwater Suction Transfer Time Delays.
- 1. Motor-Driven Pump 1/pump 1/pump 1/pump 1,2,3 21.
- 2. Turbine-Driven Pump .2/pump 1/pump 2/pump* 1,2,3 21
- Unit 1 shutdown boards only (a) One channel may be inoperable during Mode 1 for up to 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> when placing the second main feedwater (MFW) pump in service or removing one of two MFW pumps from service.
(b) When one or more Main Feedwater Pump(s) are supplying feedwaterto. steam generators.
- SEQUOYAH - UNIT 1 3/4 3-20 Amendment No. 41,129, 182, 188, 207, 301, 310, 319
(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation. of the Sequoyah and Watts Bar Unit 1 Nuclear Plants.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and. is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject .to the additional conditions specified or incorporated below:
(1) Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 312 are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading initialltest program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:
- a. Elimination of any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;
- b. Modification of test objectives, methods or acceptance criteria.for any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;
- c. Performance of any test at power level different from there described; and Facility Operating License No. DPR-79 Amendment No. 312
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL NO. MINIMUM OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION
- e. Loss of Power Start
- 1. Voltage Sensors 3/shutdown 2/shutdown 3/shutdown 1,2,3 35 board** board** board**
- 2. Load Shed Timer 2/shutdown 1/shutdown 1/shutdown 1,2,3 35 board** board** board**
- f. Trip of Main Feedwater Pumps Start Motor-Driven Pumps and Turbine Driven Pump 1/pump 1/pump 1l/pump(a) 1, 2 (b) 20
- g. Auxiliary Feedwater Suction Pressure-Low 3/pump 2/pump :3/pump 1,2,3 21
- h. Auxiliary Feedwater Suction Transfer Time Delays
- 1. Motor-Driven Pump 1/pump 1/pump 1/pump 1,2,3 21
- 2. Turbine-Driven Pump 2/pump 1/pump 2/pump 1,2,3 21
- Unit 2. Shutdown Boards Only (a) One channel may be inoperable during Mode 1 for up to 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> when placing the second main feedwater (MFW) pump in.service or removing one of two MFW pumps from service.
(b) When one or more Main Feedwater Pump(s) are supplyingfeedwater to steam generators.
SEQUOYAH - UNIT 2 3/4 3-20 Amendment No. 29, 116; 174, 180, 197, 290, 299, 312,