ML071660328
| ML071660328 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/12/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | |
| singal, balwant NRR/DORL 301-415-3016 | |
| Shared Package | |
| ML071410469 | List: |
| References | |
| TAC MD4204, TAC MD4205 | |
| Download: ML071660328 (8) | |
Text
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained inAppendix A,as revised through Amendment No. 148 ad the Environmental Protection Plan contained inAppendix 8, 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 (7) DELETED (a) DELETED (9) DELETED (10) Additional Conditions The Additional Conditions contained in Appendix D,as revised through Amendment No. 102, are hereby Incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Additional Conditions.
D. The faclity requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70.
These include (a) an exemption fmm the requirements of 10 CFR 70.24 for two criticality monitors around the fuel storage area, and (b) an exemp~on from the requirements of Paragraph IIl.D.2(b)(li) of Appendix J of 10 CFR 50, the testing of containment air locks at times when containment integrity is not required. The special circumstances regarding exemption b are identified in Section 6.2.6 of SSER 5.
An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1967, Issued August 21,1986, and relieved GPC from the requirement of having a criticality alarm system. GPC and Southern Nuclear are hereby exempted
_ caiity._a'_n sysm pro~vslon~ofJ_0CFR 70.24 sofar.as.this sec.tion.applies to the.-
from the .
storage of fuel assemblies held urider Ails license.
These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions Initems b and c above are granted pursuant to 10CFR 50.12. With License No. NPF-68 Amendment No.148
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 3565 megawatts thermal (100 percent pOwer) in accordance with the conditions specified herein.
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 128 and the Environmental Protection Plan contained in Appendix 8, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operale the facility In accordance with the Technical Specifications and the Environmental Protection Plan.
The Surveillance Requirements (SRs) contained in the Appendix ATechnical 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 lime 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) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 80, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance
.......... .. with the Additional Conditions................ . .
D. The facility requires exemptions frdm certain requirements of 10 CFR Part 50 and 10 CFR Part 70.
These include (a) an exemption from the requiremenls of 10 CFR 70.24 for two criticalty monitors around the fuel storage area, and (b) an exemption from the requirements of Paragraph IlI.D.2(b)(ii) of Appendix J of 10 CFR 50, the testing of containment air locks at times when containment Integrity isnot required. The special circumstances regarding exemption b are identified inSection 6.2.6 of SSER B.
c ens enO 'N NPF-81 men lmenV o.128
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the SLs specified in Figure 2.1.1-1.
2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained < 2735 psig.
2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2 If SL 2.1.2 is violated:
2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.
2.2.3 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> notify the NRC Operations Center, in accordance with 10 CFR 50.72.
2.2.4 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the Plant Manager and Vice President - Vogtle.
2.2.5 Within 30 days a Licensee Event Report (LER) shall be prepared and submitted to the NRC pursuant to 10 CFR 50.73.
2.2.6 Operation of the unit shall not be resumed until authorized by the NRC.
Vogtle Units 1 and 2 2.0-1 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Amendment Nos. 148, 128
Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
The Vice President - Vogtle or his designee shall approve, prior to I implementation, each proposed test, experiment, or modification to systems or equipment that affect nuclear safety.
5.1.2 A Senior Reactor Operator (SRO) shall be responsible for the control room command function while either unit is in MODES 1, 2, 3, or 4, or it is acceptable to designate an SRO as responsible for the control room command function for each unit. While both units are in MODE 5, 6, or defueled, an SRO or Reactor Operator (RO) shall be designated to assume the control room command function.
Vogtle Units 1 and 2 5.1-1 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Amendment Nos. 148, 128
Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the FSAR;
- b. The Plant Manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant;
- c. The Vice President - Vogtle shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and
- d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.
5.2.2 Unit Staff The unit staff organization shall include the following:
- a. A non-licensed operator shall be assigned to each reactor and an additional non-licensed operator shall be assigned for the control room when a reactor is operating in-MODES 1, (continued)
Vogtle Units 1 and 2 5.2-1 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Amendment Nos. 148, 128
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued) event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major plant modification, on a temporary basis the following guidelines shall be followed:
- 1. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time;
- 2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all excluding shift turnover time;
- 3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time;
- 4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the applicable department manager or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual excess overtime shall be reviewed monthly by the Plant Manager or his designee to assure that excessive hours were authorized and that they do not become routine.
- f. The Operations Manager shall hold an SRO license.
- g. An individual shall be assigned who provides technical support in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall be available for duty when the plant is in modes 1-4. At other times, this individual is not required. In addition, this individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
This position may also be filled by the Shift Superintendent or (continued)
Vogtle Units 1 and 2 5.2-3 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Amendment Nos. 148, 128
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff, including Vice President - Vogtle and Plant Manager, shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, Revision 2, 1987, and, for licensed staff, 10 CFR 55.59. Prior to meeting the recommendations of Regulatory Guide 1.8, Revision 2, personnel may be trained to perform specific tasks and will be qualified to perform those tasks independently. Personnel who complete an accredited program which has been endorsed by the NRC shall meet the requirements of the accredited program in lieu of the above.
Vogtle Units 1 and 2 5.3-1 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Amendment Nos. 148, 128
Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.
5.5.1 Offsite Dose Calculation Manual (ODCM)
- a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and
- b. The ODCM shall also contain the Radioactive Effluent Controls and Radiological Environmental Monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Specification 5.6.2 and Specification 5.6.3.
Licensee initiated changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained.
This documentation shall contain:
- 1. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s),
- 2. a determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;
- b. Shall become effective after the approval of the Vice President - Vogtle; and
- c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page (continued)
Vogtle Units 1 and 2 5.5-1 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Amendment Nos. 148, 128