ML080350349

Technical Specifications for License Amendments Regarding Measurement Uncertainty Recapture Power Uprate

ML080350349
Person / Time
Site:	Vogtle
Issue date:	02/27/2008
From:	Siva Lingam NRC/NRR/ADRO/DORL/LPLII-1
To:	Tynan T Southern Nuclear Operating Co
Lingam, Siva NRR/DORL 415-1564
Shared Package
ML080350345	List: ML080350347 ML080350349
References
Download: ML080350349 (5)

Text

B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1) Southern Nuclear, pursuant to Section 103 of the Act, and 10 CFR Part 50, to possess, manage, use, maintain, and operate the facility at the designated location in Burke County, Georgia, in accordance with the procedures and limitations set forth in this license; (2) Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, pursuant to the Act and 10 CFR Part 50, to possess, but not operate the facility at the designated location in Burke County, Georgia, in accordance with the procedures and limitations set forth in this 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; (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 authorized herein.

C. This license shall be deemed to contain and is subject to the cond'itions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable pr'ovisions 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 Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3625.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.

Amendment No. 149

(2) Technical Specifications and Environmental -Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 14 9,and the Environmental Protection Plan contained in Appendix B, both of which-are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Southern Nuclear Operating Company shall be capable of establishing containment hydrogen monitoring within 90 minutes of initiating safety injection following a loss of coolant accident.

(4) DELETED (5) DELETED (6) DELETED

()DELETED (8) DELETED (9) DELETED (10) Mitigation Strategy License Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets 2., Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of read ily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders Amendment No. 149

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 Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3625.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as re vised through Amendment No. 1429nd the Environmental Protection Plan contained in Appendix B, both of which are attached. hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

The Surveillance. Requirements (SRs) contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment No. 74. The SRs listed below shall be successfully demonstrated prior to the time and condition specified below for each:

a) DELETED b) DELETED c) SR 3.8.1.20 shall be successfully demonstrated at the first regularly scheduled performance after implementation of this license amendment.

(3) Southern Nuclear Operating Company shall be capable of establishing

.containment hydrogen monitoring within 90 minutes of initiating safety injection following a loss of coolant accident.

(4) Mitigation Strategy License Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mUtual'aid fire figh ting assets

3. Designated staging areas. for equipment and materials

4. Command and control

5. Training of response personnel Amendment No. 129

Definitions 1.1 1.1 Definitions (continued)

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determ~ination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL OPERATIONAL A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required TEST (COT) alarm, interlock, and trip functions. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or other reactivity control components within the reactor Vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determidned for each reload cycle in accordance with Specification 5.6.5. Unit operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-1,31, 1-132, 1-133,1-134, and 1-135 actually present. The thyroid dose conversion fadtors-used for this calculation shall be those listed in EPA Federal Guidance Report No. 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion,

.and Ingestion," EPA-520/11-88-020, September 1988.

(continued)

Vogtle Units I and 2 1.1-2 Amendment No.149 (Unit 1)

Amendment No. 129 (Unit 2)

Definitions 1.1 Definitions PHYSICS TESTS a. Described in Chapter 14 of the FSAR; (continued)

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates, Cold Ovrerpressure Protection System (COPS) arming temperature and the nominal PORV setpoints for the COPS, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.6. Unit operation within these operating limits is addressed in individual specifications.

QUADRANT POWER'TILT QPTR shall be the ratio of the maximum upper RATIO (QPTR) excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 3625.6 MV~k., I REACTOR TRIP The RTS RESPONSE TIME shall be that time interval SYSTEM (RTS) RESPC )NSE from when the monitored parameter exceeds its RTS TIM E trip setpoint at the channel sensor until loss of stationary-gripper coil voltage. The response tim-e may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC.

(continued)

Vogtle Units 1 and 2 1'.1-5 Amendment No. 149 (Unit 1)

Amendment No. 129 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 50of9)

Reactor Trip System Instrumentation APPLICABLE MODES OR NOMINAL OTHER TI SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE STRCIPT )

FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SEPNT~

14. Turbine Trip

a. Low Fluid Oil 10) 3 0 SIR 3.3.1.10 '?500 psig 580 psig, Pressure SR 3.3.1.16

b. Turbine Stop 10) 4 P SR 3.3.1.10 Ž90% open 96.7% open Valve Closure SR 3.3.1.14

15. Safely Injection (SI) 1.2 2 trains o SR 3.3.1.13 NA NA Input from Engineered Safety Feature Actuation System (ESFAS)

16. Reactor Trip System Interlocks

a. Intermediate 2 (d) 2 R SR 3.3.1.11 S1.2E-5% RIP 2.02-5% RIP Range

• SIR 3.3.1.12 Neutron Flux, P-6

b. Low Power 1 1 per train S) SR 3.3.1.5 NA NA Reactor Trips Block, P-7

c. PowerRange 4 S SR 3.3.1.11 5 50.3% RIP 48% RTPý Neutron Flux. SIR 3.3.1.12 P-8 1

d. Power Range S SIR 3.3.1.11 *40.6% RTP 40% RIP.

Neutron Flux, SIR 3.3.1.12 P-9 1,2

e. Power Range 4 R SIR 3.3.1.11 (I'M)

Neutron Flux, (t.m)

• ,P-10 and input SIR 3.3.1.12 to6P-7.

1

f. Turbine 2 S SIR 3.3.1.10 S12.3% Impulse 10% Impulse Impulse SIR 3.3.1.12 Pressure Pressure Pressure. Equivalent Equivalent P-13 turbine turbine (continue~d)

(d) Below the P-6 (intermediate Range Neutron Flux) Interlocks.

Above the P-9 (Power Range Neutron Flux) interlock.

For the P-10 Input to P-7, the Allowable Value Is !512.3% RTP and the Nominal Trip Setpoint Is 10% RTP.

(in)

For the Power Range Neutron Flux, P-10, the Allowable Value is 2t7.7% RIP and the Nominal Trip Setpoint is 10% RIP.

A channel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpolnt value.

is conservative with respect to its associated Allowable Value and the channel Is readjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative then the Nominal Trip Setpoint as necessary in response to plant conditions Vogtle Units 1 and 2 3.3.1-18 Amendment No. 149(Unit 1)

Amendment No. 129(Uflit 2)