ML082750299
| ML082750299 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/29/2008 |
| From: | Richard Guzman Plant Licensing Branch 1 |
| To: | Polson K Nine Mile Point |
| Guzman R | |
| References | |
| TAC MD7529, TAC MD7530 | |
| Download: ML082750299 (4) | |
Text
-3 (3)
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; (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 analysis or instrument and equipment calibration or 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 the operation of the facility.
C.
This renewed operating 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; Section 50.54 and 50.59 of Part 50; and Section 70.32 of Part 70. This renewed license 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 also subject to the additional conditions specified or incorporated below:
(1 )
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1850 megawatts (thermal).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 198, is hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications.
(3)
Deleted Renewee License No. DPR 63 Amendment No. 191, 192, 19a, 194,195,196,197,198
Any deviation from the above guidelines shall be authorized in advance by the plant manager or the plant manager's designee, in accordance with approved administrative procedures, with documentation of the basis for granting the deviation. Routine deviation from the work hour guidelines shall not be authorized.
Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned.
- e. As a minimum, either the Manager Operations or the General Supervisor Operations shall hold an SRO license.
- f.
The Shift Technical Advisor (STA) shall provide advisory technical support to the shift supervision in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
6.3 Unit Staff Qualifications 6.3.1 Each member of the unit staff, with the exception of the operator license applicants and the radiation protection manager, shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The education and experience eligibility requirements for operator license applicants. and changes thereto, shall be those previously reviewed and approved by the NRC; specifically. those referenced in letter NMP1L 2184, dated December 20,2007, and described in applicable station training procedures.
6.3.2.
For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of Specification 6.3.1, perform the functions described in 10 CFR 50.54(m).
6.4 Procedures 6.4.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Section 5.1 and 5.3 of ANSI N18.7-1972 and cover the following activities:
- a.
The applicable procedure recommended in Regulatory Guide 1.33, Appendix A, November 3, 1972; AMENDMENT NO. 142. 157. 158. 160. 162. 181. 198 349
-4 (1 )
Maximum Power Level Nine Mile Point Nuclear Station, LLC is authorized to operate the facility at reactor core power levels not in excess of 3467 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, both of which are attached hereto, as revised through Amendment No. 127 are hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Fuel Storage and Handling (Section 9.1, SSER 4)*
- a.
Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
- b.
When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility.
- c.
The above three fuel assemblies shall maintain a minimum edge to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
- d.
The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at anyone time.
(4)
Turbine System Maintenance Program (Section 3.5.1.3.10, SER)
The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities.
(SUbmitted by NMPC letter dated October 30, 1989 from C.D. Terry and approved by NRC letter dated March 15,1990 from Robert Martin to Mr. Lawrence Burkhardt, III).
The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.
Renewed License No: NPF 69 Amendment 117 throl:lgh 125,126,127
5.3.1 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications Each member of the unit staff, with the exception of the operator license applicants and the radiation protection manager, shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 for comparable positions.
The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The education and experience eligibility requirements for operator license applicants, and changes thereto, shall be those previously reviewed and approved by the NRC; specifically, those referenced in letter NMP1L 2184, dated December 20,2007, and described in applicable station training procedures.
5.3-;
Amendment 9-l, ; 27