ML081410170

Technical Specifications, Addition of Engineered Safety Features Room Cooler TS

ML081410170
Person / Time
Site:	Farley
Issue date:	06/27/2008
From:	NRC/NRR/ADRO/DORL/LPLII-1
To:
Jervey, Richard 301-415-2728
References
TAC MD5778, TAC MD5779
Download: ML081410170 (5)

Text

(2)

Technical Specifications The Technical Soecifications contained in Appendix A, as revised through Amendment No

_176, 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.

176 (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 Commissions's 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.

169, are hereby incorporated in the renewed license.

Southern Nuclear snall operate the facility in accordance with the Technical Specifications.

Farley - Unit 2 Renewed License No. NPF-8.

Amendment No. 169

TABLE OF CONTENTS 3.7.3 Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves...................... 3.7.3-1 3.7.4 Atmospheric Relief Valves (ARVs)..................................................

3.7.4-1 3.7.5 Auxiliary Feedwater (AFW ) System.................................................

3.7.5-1 3.7.6 Condensate Storage Tank (CST)....................................................

3.7.6-1 3.7.7 Component Cooling Water (CCW ) System.....................................

3.7.7-1 3.7.8 Service Water System (SW S)..........................................................

3.7.8-1 3.7.9 Ultimate Heat Sink (UHS)................................................................

3.7.9-1 3.7.10 Control Room Emergency Filtration/Pressurization System (CREFS).......................................................................

3.7.10-1 3.7.11 Control Room Air Conditioning System (CRACS)........................... 3.7.11-1 3.7.12 Penetration Room Filtration (PRF) System.....................................

3.7.12-1 3.7.13 Fuel Storage Pool W ater Level........................................................

3.7.13-1 3.7.14 Fuel Storage Pool Boron Concentration..........................................

3.7.14-1 3.7.15 Spent Fuel Assembly Storage.........................................................

3.7.15-1 3.7.16 Secondary Specific Activity............................................................

3.7.16-1 3.7.17 Cask Storage Area Boron Concentration - Cask Loading Operations...........................................

............................. 3.7.17-1 3.7.18 Spent Fuel Assembly Storage -Cask Loading Operations............ 3.7.18-1 3.7.19 Engineered Safety Feature (ESF) Room Coolers............

3.7.19-1 3.8 ELECTRICAL POWER SYSTEMS..........................................................

3.8.1-1 3.8.1 AC Sources-Operating.................................................................

3.8.1-1 3.8.2 AC Sources-Shutdown.................................................................

3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air.......................................

3.8.3-1 3.8.4 DC Sources - Operating.................................................................

3.8.4-1 3.8.5 DC Sources-Shutdown................................................................

3.8.5-1 3.8.6 Battery Cell Parameters...................................................................

3.8.6-1 3.8.7 Inverters -

Operating......................................................................

3.8.7-1 3.8.8 Inverters -

Shutdown......................................................................

3.8.8-1 3.8.9 Distribution Systems - Operating...................................................

3.8.9-1 3.8.10 Distribution Systems-Shutdown...................................................

3.8.10-1 3.9 REFUELING OPERATIONS................................................... 3.9.1-1 3.9.1 Boron Concentration........................................................................

3.9.1-1 3.9.2 Nuclear Instrumentation..................................................................

3.9.2-1 3.9.3 Containment Penetrations...............................................................

3.9.3-1 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level.................................................

3.9.4-1 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation -

Low Water Level..................................................

3.9.5-1 3.9.6 Refueling Cavity Water Level..........................................................

3.9.6-1 4.0 DESIGN FEATURES..............................................................................

4.0-1 4.1 Site Location..................................................................................

4.0-1*'

4.2 Reactor Core...................................................................................

4.0-1 Farley Units 1 and 2 iii Amendment No. 1 76 (Unit 1)

Amendment No.169 (Unit 2)

ESF Room Coolers 3.7.19 3.7 PLANT SYSTEMS 3.7.19 Engineered Safety Feature (ESF) Room Coolers LCO 3.7.19 APPLICABILITY:

ESF Room Coolers shall be OPERABLE.

When associated ESF equipment is required to be OPERABLE.

ACTIONS NOTE----

Separate Condition entry is allowed for each ESF Room Cooler subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One required ESF Room A.1 Restore the affected ESF Room 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Cooler subsystem Train Cooler subsystem Train to inoperable.

OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not met.

AND OR B.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Two trains of the same ESF Room Cooler subsystem inoperable.

Farley Units 1 and 2 3.7.19-1 Amendment No. 176 (Unit 1)

Amendment No. 169 (Unit 2)

ESF Room Coolers 3.7.19 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.19:1 Vedfy each ESF Room Cooler system manual valve 31 days servicing safety-related equipment that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.19.2 Verify each ESF Room Cooler fan starts 18 months automatically on an actual or simulated actuation signal.

Farley Units 1 and 2 3.7.19-2 Amendment No.176 (Unit 1)

Amendment No.169 (Unit 2)