ML070590508

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License and Technical Specification Pages - Amendment No. 248 to Facility Operating License Relocation of T.S. 2.22, Toxic Gas Monitors, and T.S. Table 3-3, Item 29 to Updated Safety Analysis Report
ML070590508
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 02/28/2007
From: Wang A
NRC/NRR/ADRO/DORL/LPLIV
To: Ridenoure R
Omaha Public Power District
Wang A, NRR/DORL/LPL4, 301-415-1445
Shared Package
ML063520137 List:
References
TAC MD3668
Download: ML070590508 (6)


Text

(4) 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 arailysis or instrument calibration or when associated with radioactive apparatus or components; (5) 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 faciliy.

3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of 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 Omaha Public Power District is authorized to operate the Fort Calhoun Station, Unit 1, at steady state reactor core power levels not in excess of 1500 megawatts thermal (rated power).

B. Technical Specifications The Technical Specifications contained In Appendix A, as revised through Amendment No, 248 are hereby incorporated In the license. Omaha Public Power District shall operate the facility in accordance with th* Technical Specifications.

C. Security and Safegurds Contingqency Plans The Omaha Public Power District shall fully Implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans Including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FFR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, Which contain Safeguards Information protected under 10 CFR 73.21, are entitled: ."Fort Calhoun Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan,' submitted by letter dated May 19, 2006, Renewed Operating License No. DPFI-40 Amendment No. 248

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued) 2.13 DELETED 2.14 Engineered Safety Features System Initiation Instrumentation Settings 2.15 Instrumentation and Control Systems 2.16 River Level 2.17 Miscellaneous Radioactive Material Sources 2.18 DELETED 2.19 DELETED 2.20 Steam Generator Coolant Radioactivity 2.21 Post-Accident Monitoring Instrumentation 2.22 DELETED 2.23 Steam Generator (SG) Tube Integrity 3.0 SURVEILLANCE REQUIREMENTS 3.1 Instrumentation and Control 3.2 Equipment and Sampling Tests 3.3 Reactor Coolant System and Other Components Subject to ASME XI Boiler and Pressure Vessel Code Inspection and Testing Surveillance 3.4 DELETED 3.5 Containment Test 3.6 Safety Injection and Containment Cooling Systems Tests 3.7 Emergency Power System Periodic Tests 3.8 Main Steam Isolation Valves 3.9 Auxiliary Feedwater System 3.10 Reactor Core Parameters 3.11 DELETED 3.12 Radioactive Waste Disposal System 3.13 Radioactive Material Sources Surveillance 3.14 DELETED 3.15 DELETED 3.16 Residual Heat Removal System Integrity Testing 3.17 Steam Generator (SG) Tube Integrity 4.0 DESIGN FEATURES 4.1 Site 4.2 Reactor Core 4.3 - Fuel Storage TOC - Page 2 Amendment No. 11,27,32,38,13,16,51,60,84,86, 93,97,104,122,136,152,160, 176,183, 211,230, 236,4 ra, 248

TECHNICAL SPECIFICATIONS TECHNICAL SPECIFICATIONS - TABLES TABLE OF CONTENTS TABLE SECTION 1-1 R P S LS S S ................................................................................................................................. S e ction 1.0 2-1 ESFS Initiation Instrumentation Setting Limits ........................................................................ Section 2.14 2-2 Instrument Operating Requirements for RPS ......................................................................... Section 2.15 2-3 Instrument Operating Requirements for Engineered Safety Features .................................... Section 2.15 2-4 Instrument Operating Conditions for Isolation Functions ........................................................ Section 2.15 2-5 Instrumentation Operating Requirements for Other Safety Feature Functions ...................... Section 2.15 2-9 R C S Pressure Isolation V alves ................................................................................................. Section 2.1 2-10 Post-Accident Monitoring, Instrumentation Operating Limits .................................................. Section 2.21 3-1 Minimum Frequencies for Checks, Calibrations, and Testing of RPS ...................................... Section 3.1 3-2 Minimum Frequencies for Checks, Calibrations and Testing of ............................................... Section 3.1 Engineered Safety Features, Instrumentation and Controls 3-3 Minimum Frequencies for Checks, Calibrations, and Testing .................................................. Section 3.1 of Miscellaneous Instrumentation and Controls 3-3a Minimum Frequency for Checks, Calibrations and Functional .................................................. Section 3.1 Testing of Alternate Shutdown Panels (Al-1 85 and AI-212) and Emergency Auxiliary Feedwater Panel (AI-179) Instrumentation and Control Circuits 3-4 Minimum Frequencies for Sampling Tests ................................................................................ Section 3.2 3-5 Minimum Frequencies for Equipment Tests .............................................................................. Section 3.2 3-6 Reactor Coolant Pump Surveillance .................................................................................... Section 3.3 TOC - Page 4 Amendment No. 46,6,16024A 248

TECHNICAL SPECIFICATIONS TECHNICAL SPECIFICATIONS - TABLES TABLE OF CONTENTS (ALPHABETICAL ORDER)

Continued TABLE DESCRIPTION SECTION 2-10 Post-Accident Monitoring Instrumentation Operating Limits ................................................... Section 2.21 2-9 R C S P ressure Isolation V alves ................................................................................................. Section 2 .1 3-6 Reactor Coolant Pump Surveillance ....................................... Section 3.3 1-1 R PS LS S S ................................................................................................................................. S e ction 1 .0 TOC - Page 7 Amendment No. 116,145,152,176, 195, 246, 248

TECHNICAL SPECIFICATIONS Not Used 2.22 - Page 1 Amendment No. 87, 248

TECHNICAL SPECIFICATIONS TABLE 3-3 (Continued)

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Description Function Frequency Surveillance Method

25. Containment Purae Is olation a. Check M a. Verifv valve Dos 3ition using control Valves (PCV-742A, B, C, & D) room indication.
26. Not Used
27. Containment Water Level a. Check M a. CHANNEL CHECK Narrow Range (LT-599

& LT.-600) b. Calibrate R b. CHANNEL CALIBRATION Wide Range (LT-387 & a. Check M a. CHANNEL CHECK LT-388)

b. Calibrate R b. CHANNEL CALIBRATION
28. Containment Wide Range a. Check M a. CHANNEL CHECK Pressure Indication
b. Calibrate R b. CHANNEL CALIBRATION
29. Not Used 3.1 - Page 19 Amendment No. 54,68,82,87,107,182, 183, 2314 248