ML081660009
| ML081660009 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/02/2008 |
| From: | NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | |
| Jervey, Richard 301-415-2728 | |
| Shared Package | |
| ML081630497 | List: |
| References | |
| TAC MD7391, TAC MD7394 | |
| Download: ML081660009 (3) | |
Text
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 177, are hereby incorporated in the renewed license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
(3)
Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the renewed license or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission.
a.
Southern Nuclear shall not operate the reactor in Operational Modes 1 and 2 with less than three reactor coolant pumps in operation.
b.
Deleted per Amendment 13 c.
Deleted per Amendment 2 d.
Deleted per Amendment 2 e.
Deleted per Amendment 152 Deleted per Amendment 2 f.
Deleted per Amendment 158 g.
Southern Nuclear shall maintain a secondary water chemistry monitoring program to inhibit steam generator tube degration.
This program shall include:
1)
Identification of a sampling schedule for the critical parameters and control points for these parameters; 2)
Identification of the procedures used to quantify parameters that are critical to control points; 3)
Identification of process sampling points; 4)
A procedure for the recording and management of data; Farley - Unit 1 Renewed License No. NPF-2 Amendment No. 177 (2)
Alabama Power Company, pursuant to Section 103 of the Act and 10 CFR Part 50, Licensing of Production and Utilization Facilities, to possess but not operate the facility at the designated location in Houston County, Alabama in accordance with te procedures and limitations set forth in this renewed license.
(3)
Southern Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)
Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
Southern Nuclear, 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 (6)
Southern Nuclear, 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 facility.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissionss regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and 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 Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 2775 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 170, are hereby incorporated in the renewed license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
Farley - Unit 2 Renewed License No. NPF-8 Amendment No. 170
5.5 Programs and Manuals 5.5 Programs and Manuals 5.5.15 Safety Function Determination Program (SFDP) (continued)
- b.
A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or
- c.
A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.
The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.
5.5.16 Main Steamline Inspection Program The three main steamlines from the rigid anchor points of the containment penetrations downstream to and including the main steam header shall be inspected. The extent of the inservice examinations completed during each inspection interval (IWA 2400, ASME Code, 1974 Edition,Section XI) shall provide 100 percent volumetric examination of circumferential and longitudinal pipe welds to the extent practical. The areas subject to examination are those defined in accordance with examination category C-G for Class 2 piping welds in Table IWC-2520.
5.5.17 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of containment as required by 10 CFR 50.54 (0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception to NEI 94-01, Rev. 0, "Industry Guidelines for Implementing Performance-Based Option of 10 CFR 50, Appendix J":
Section 9.2.3: The next Type A test, after the March 1994 test for Unit 1 and the March 1995 test for Unit 2, shall be performed during refueling outage R22 (Spring 2009) for Unit 1 and during refueling outage R20 (Spring 2010) for Unit 2. This is a one time exception.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 43.8 psig.
The maximum allowable containment leakage rate, La, at Pa, is 0.15% of containment air weight per day.
(continued)
Farley Units 1 and 2 5.5-13 Amendment No.
(Unit 1)
Amendment No.
(Unit 2) 177 170