ML062080348
| ML062080348 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/24/2005 |
| From: | NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | |
| References | |
| TAC MC8427 | |
| Download: ML062080348 (2) | |
Text
instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
ENO pursuant to the Act and 10 CFR Parts 30, 40 and 70, Amdt. 42 to receive, possess, and use in amounts as required any 10-17-78 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; (5)
ENO pursuant to the Act and 10 CFR Parts 30 and 70, to Amdt. 220 possess, but not separate, such byproduct and special 09-06-01 nuclear materials as may be produced by the operation of the facility.
C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 ENO is authorized to operate the facility at steady state Amdt. 241 reactor core power levels not in excess of 3216 10-27-04 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 248, are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications.
(3) The following conditions relate to the amendment approving the conversion to Improved Standard Technical Specifications:
- 1. This amendment authorizes the relocation of certain Technical Specification requirements and detailed information to licensee-controlled documents as described in Table R, "Relocated Technical Specifications from the CTS," and Table LA, "Removed Details and Less Restrictive Administrative Changes to the CTS" attached to the NRC staff's Safety Evaluation enclosed with this amendment. The relocation of requirements and detailed information shall be completed on or before the implementation of this amendment.
Amendment No. 248
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 8.
Technical Specification 3.2.3, Axial Flux Difference (AFD);
- 9.
Technical Specification 3.3.1, Reactor Protection System Instrumentation;
- 10.
Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits; and
- 11.
Technical Specification 3.9.1, Boron Concentration.
- b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985;
- 2.
WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report", September 1974;
- 3.
T.M. Anderson to K. Kniel (NRC) January 31, 1980 -
Attachment:
Operation and Safety Analysis Aspects of an Improved Load Follow Package;
- 4.
NUREG-0800, Standard Review Plan, US Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981, including Branch Technical Position CPB 4.3-1,Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981;
- 5.
.WCAP-11397-P-A, "Revised Thermal Design Procedure", April 1989;
- 6.
WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM)," M. E. Nissley, et al., January 2005.
- 7.
WCAP-8745-P-A, Design Bases for the Thermal Overpower Delta-7T and Thermal Overtemperature Delta-T Trip Functions",
September 1986; INDIAN POINT 2 5.6-3 Amendment No. 248