ML081420044
| ML081420044 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/17/2008 |
| From: | NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | |
| Lingam, Siva NRR/DORL 415-1564 | |
| Shared Package | |
| ML081420040 | List: |
| References | |
| TAC MD5877, TAC MD5878 | |
| Download: ML081420044 (3) | |
Text
3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; 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 below:
A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2546 megawatts (thermal).
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No49, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
C. Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.
D. Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E. Deleted by Amendment 65 F. Deleted by Amendment 71 G. Deleted by Amendment 227 H. Deleted by Amendment 227 I. Fire Protection The licensee shall implement and maintain in effect the provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the SER dated September 19, 1979, (and Supplements dated May 29, 1980, October 9, 1980, December 18, 1980, February 13, 1981, December 4, 1981, April 27,1982, November 18, 1982, January 17, 1984, February 25, 1988, and SURRY UNIT 1 Renewed License No. DPR-32 Amendment No. 259 E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility."
- 3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; 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 below:
A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2546 megawatts (thermal).
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 259, are hereby incorporated in this renewed license.
The licensee shall operate the facility in accordance with the Technical Specifications.
C. Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.
D. Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E. Deleted by Amendment 54 F. Deleted by Amendment 59 and Amendment 65 G. Deleted by Amendment 227 H. Deleted by Amendment 227 SURRY - UNIT 2 Renewed License No. DPR-37 Amendment No. 259
TS 3.8-4 (3) assuring that environmental conditions will not preclude access to close the valves and
- 4) that this administrative or manual action wiii prevent the release of radioactivity outside the containment.
The Reactor Coolant System temperature and pressure being below 350'F and 450 psig, respectively, ensures that no significant amount of flashing steam will be formed and hence that there would be no significant pressure buildup in the containment if there is a loss-of-coolant accident. Therefore, the containment internal pressure is not required to be subatmospheric prior to exceeding 350'F and 450 psig.
The allowable value for the containment air partial pressure is presented in TS Figure 3.8-1 for service water temperatures from 25 to 100°F. The RWST water shall have a maximum temperature of 45°F.
The horizontal upper limit line in TS Figure 18-1 is based on MSLB peak calculated pressure criteria, and the sloped line from 70'F to 100°F service water temperatures is based on LOCA depressurization criteria.
AmendmentNos. 259 and 259
TS Figure 3.8-1 SURRY TECHNICAL SPECIFICATION CURVE FOR CONTAINMENT ALLOWABLE AIR PARTIAL PRESSURE INDICATION VS. SERVICE WATER TEMPERATURE 11.6 11.4 11.2 11.0 w
10.8 a.
,a 10.6 (D
z 10.4 10.2 10.0 (100, 10.3)
-,(100, 10.1) 85 90 95 100 105 20 25 30 35 40 45 50 55 60 65 70 75
- 80 Service Water Temperature, deg-F I Note: Operation on or outside the line requires entry into TS 3.8.D. L.a t