ML062710022
| ML062710022 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/22/2006 |
| From: | NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Carolina Power & Light Co |
| Patel C, NRR/DORL/LPL2-2, 415-3025 | |
| Shared Package | |
| ML062380004 | List: |
| References | |
| TAC MC4219 | |
| Download: ML062710022 (4) | |
Text
neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D.
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 and equipment calibration or associated with radioactive apparatus or components; 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 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, Section 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 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:
A.
Maximum Power Level The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal.
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
are hereby incorporated in the license.
The license shall operate the facility in accordance with the Technical Specifications.
(1)
For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment1 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176.
Renewed Facility Operating License No. DPR-23 Amendment No. 210
RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 7)
Reactor Protection System Instrumentation APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCT I ON CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)
- 1.
Manual Reactor Trip 1,2 2
B SR 3.3.1.14 NA NA 3 (a),
4 (a),
5 (a) 2 C
SR 3.3.1.14 NA NA
- 2.
Power Range Neutron FI,x
- a.
High 1,2 4
< 110.93%
108%
SR 3.3.1.2 RTP RTP (2)
SR 3.3.1.7 SR 3.3.1.11
- b.
Low 1(b), 2 4
- 26.93%
SR 3.3.1.8 RTP 24% RTP SR 3.3.1.11
- 3.
Int:ermediate Range 1(b),
2 (c) 2 F,G SR 3.3.1.1
< 36.40%
25% RTP Neutron Flux SR 3.3.1.8 RTP SR 3.3.1.11 2(d) 2 H
< 36.40%
25% RTP SR 3.3.1.8 RTP SR 3.3.1.11
- 4.
Source Range Neutron SR 3.3.1.1
< 1.28 E5 1.0 E5 Flux 2 (d) 2 IJ SR 3.3.1.8 cps cps SR 3.3.1.11 SR 3.3.1.1
< 1.28 E5 1.0 E5 3 (a),
4 (a),
5 (a) 2 J,K SR 3.3.1.7 cps cps SR 3.3.1.11 SR 3.3.1.1 N/A N/A 3 (e),
4 (e),
5 (e) 1 L
SR 3.3.1.11 (continued)
(1)
A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.
(2)
The Nominal Trip Setpoint is as stated unless reduced as required by one or more of the following requirements:
LCO 3.2.1 Required Action A.2.2; LCO 3.2.2 Required Action A.1.2.2; or LCO 3.7.1 Required Action B.2.
(a)
With Red Control System capable of rod withdrawal, or one or more rods not fully inserted.
(b)
Below the P-1O (Power Range Neutron Flux) interlock.
(c)
Above the P-6 (Intermediate Range Neutron Flux) interlock.
(d)
Below the P-6 (Intermediate Range Neutron Flux) interlock.
(e)
With the RTBs open.
In this condition, source range Function does not provide reactor trip but does provide indication and alarm.
HBRSEP Unit No. 2 3.3-13 Amendment No.210
RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 7)
Reactor Protection System Instrumentation APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)
- 14.
SR 3.3.1.1 k 29.36%
30%
Level - Low SR 3.3.1.7 SR 3.3.1.10 Coincident with 1,2 2 per SG E
- 7.01 E5 6.4 ES Steam SR 3.3.1.7 Ibm/hr Ibm/hr Flow/Feedwater Flow SR 3.3.1.10 Mismatch
- 15.
- a. Low Auto Stop lCf)
SR 3.3.1.10 5 40.87 45 psig Oil Pressure SR 3.3.1.15 psig
- b. Turbine Stop Valve Closure 1(f) 2 P
SR 3.3.1.15 NA NA
- 16.
Safety 1,2 2 trains Q
SR 3.3.1.14 NA NA Irjection (SI)
Input from Erigineered Safety Feature Actuation System (ESFAS)
(continued)
(1)
A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.
(f)
Above the P-7 (Low Power Reactor Trips Block) interlock.
HBRSEP Unit No. 2 3.3-16 Amendment N0.210
RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 7)
Reactor Protection System Instrumentation APPLICABLE MODES NOMINAL OR OTHER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SETPOINT FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (1)
- 17.
Reactor Protection System Interlocks
- a.
Intermediate 2 (d) 2 S
SR 3.3.1.11 k 9.34 1 E-1O Range Neutron SR 3.3.1.13 E-11 amp amp Flux, P-6
- b.
Low Power 1
1 per T
SR 3.3.1.13 NA NA Reactor Trips train SR 3.3.1.14 Block, P-7
- c.
Power Range 1
4 T
SR 3.3.1.11 g 42.94%
40% RTP Neutron Flux, SR 3.3.1.13 RTP P-8
- d.
Power Range 1,2 4
S SR 3.3.1.11 k 7.06%
10% RTP Neutron Flux, SR 3.3.1.13 RTP and g P-10 12.94%
- e.
Turbine Impulse 1
2 T
< 10.71%
10%
Pressure, P-7 SR 3.3.1.10 turbine turbine input SR 3.3.1.13 power power
- 18.
Reiactor Trip 1,2 2 trains R,V SR 3.3.1.4 NA NA Bre.akers( i) 3 (a),
4 (a), 5 (a) 2 trains CV SR 3.3.1.4 NA NA
- 19.
Reactor Trip 1,2 1 each U
SR 3.3.1.4 NA NA Breaker per RTB UniJervoltage and Shunt Trip 3 (a),
4 (a),
5 (a) 1 each C
SR 3.3.1.4 NA NA Mechan isms per RTB
- 20.
Aul:omatic Trip 1, 2 2 trains QV SR 3.3.1.5 NA NA Loilic 3 (a),
4 (a),
5 (a) 2 trains CV SR 3.3.1.5 NA NA (1)
A channel is OPERABLE with an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint.
(a)
With Rod Control System capable of rod withdrawal, or one or more rods not fully inserted.
(d)
Below the P-6 (Intermediate Range Neutron Flux) interlock.
(i)
Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.
(j)
Not used.
I HBRSEP Uniit No. 2 3.3-17 Amendment No. 210