ML072470748
| ML072470748 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 08/31/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Carolina Power & Light Co |
| Vaaler, Marlayna, NRR/DORL 415-1998 | |
| Shared Package | |
| ML071980480 | List: |
| References | |
| TAC MD2723 | |
| Download: ML072470748 (3) | |
Text
(1)
Maximum Power Level Carolina Power & Light Company is authorized to operate the facility at reactor core power levels not in excess of 2900 megawatts thermal (100 percent rated core power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No.
, are hereby incorporated into this license.
Carolina Power & Light Company shall operate the facility in accordance with te Technical Specifications and the Environmental Protection Plan.
(3)
Antitrust Conditions Carolina Power & Light Company shall comply with the antitrust conditions delineated in Appendix C to this license.
(4)
Initial Startup Test Program (Section 14)1 Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(5)
Steam Generator Tube Rupture (Section 15.6.3)
Prior to startup following the first refueling outage, Carolina Power & Light Company shall submit for NRC review and receive approval of a steam generator tube rupture analysis, including the assumed operator actions, which demonstrates that the consequences if the design basis steam generator tube rupture event for the Shearon Harris Nuclear Power Plant are less than the acceptance criteria specified in the Standard Review Plan, NUREG-0800, at §15.6.3 Subparts 11(1) and (2) for calculated doses from radiological releases. In preparing their analysis Carolina Power & Light Company will not assume that operators will complete corrective actions within the first thirty minutes after a steam generator tube rupture.
1The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Amendment No. 126
TABLE 2.2-1 (continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL ALLOWANCE FUNCTIONAL UNIT (TA)
SENSOR ERROR z
(S)
TRIP SETPOINT ALLOWABLE VALUE 89.5% of loop indicated flow
- 12.
Reactor Coolant Flow-Low
- 13.
Steam Generator Water Level Low-Low
- 14.
Steam Generator Water Level Low Coincident With Steam/Feedwater Flow Mismatch
- 15.
Undervoltage - Reactor Coolant Pumps
- 16.
Underfrequency - Reactor Coolant Pumps
- 17.
- a. LOw Fluid Oil Pressure
- b. Turbine Throttle Valve Closure
- 18.
Safety Injection Input from ESF RTP = RATED THERMAL POWER 4.58 25.0 8.9 20.0 14.0 5.0 1.98 0.6 17.45 2.0 5.95 2.0
> 90.5% of loop full indicated flow
> 25.0% of narrow range instrument span
> 25.0% of narrow range instrument span full 3.01 Note 6
- 40% of full flow at RTP** steam
> 23.5% of narrow range instrument span
> 24.05% of narrow range instrument span
<43.1% of full steam flow at RTP**
4920 volts 57.3 Hz 1.3 0.0 3.0 0.0 5148 volts 57.5 Hz N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
1000 psig
> 1% open 950 psig 1% open N.A.
N.A.
SHEARON HARRIS
- UNIT 1 2-5 Amendment No.126
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TOTAL ALLOWANCE (TA)
SENSOR ERROR z
(S) 8.15 2.0 5..
Turbine Trip and Feedwater Isolation (Continued)
- b.
Steam Generator Water Level--High-High (P-14) 22.0 TRIP SETPOINT
- 78.0% of narrow range instrument span.
ALLOWABLE VALUE
- 79.5% of narrow range instrument span.
C.
Safety Injection See Item 1. above for Allowable Values.
.Safety Injection Trip Setpoints and
- 6.
- a.
Manual Initiation
- b.
Automatic Actuation Logic and Actuation Relays
- c.
Steam Generator Water Level--Low-Low
- d.
Safety InjectionStart Motor-Driven Pumps
- e.
Loss-of-Offsite Power Start Motor-Driven Pumps and Turbine-Driven Pump
- f.
Trip of All Main Feedwater Pumps Start Motor-Driven Pumps N.A.
N.A.
25.0 N.A.
N.A.
. N.A.
N.A.
N.A.
N.A.
N.A.
17.45 2.0 N.A.
Ž 25.0% of narrow range instrument span.
Ž 23.5% of narrow range instrument span.
See Item 1. above for Allowable Values.
See Item 9. below for Allowable Values.
all Safety Injection Trip Setpoints and all Loss-of-Offsite Trip Setpoint and N.A.
N.A.
N.A.
N.A.
N.A.
SHEARON HARRIS - UNIT 1 3/4 3-32 Amendment No. 126