ML071590020
| ML071590020 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/07/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | |
| Martin R, NRR/DORL, 415-1493 | |
| Shared Package | |
| ML071220286 | List: |
| References | |
| TAC MD4202, TAC MD4203 | |
| Download: ML071590020 (16) | |
Text
for sample analysis or Instrument calibration, or associated with radioactive apparatus or components; (6) Southern Nuclear, 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 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 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter In effect; and the additional conditions specified or Incorporated below;.
(1) Maximum Power Level Southern Nuclear is authorized to operate the facility at steady state reactor core power levels not Inexcess of 2804 megawatts thermal.
(2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 252 are hereby Incorporated Inthe renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
The Surveillance Requirement (SR) contained in the Technical Specifications and listed below, is not required to be performed Immediately upon Implementation of Amendment No. 195. The SR listed below shall be successfully demonstrated prior to the time and condition specified:
SR 3.8.1.18 shall be successfully demonstrated at its next regularly scheduled performance (3) Fire Protection Southern Nuclear shall Implement and maintain In effect all provisions of the fire protection program, which Is referenced In the Updated Final Safety Analysis Report for the facility, as contained In the updated Fire Hazards Analysis and Fire Protection Program for Edwin I. Hatch Nuclear Plant Units I and 2, which was originally submitted by letter dated July 22, 1986; Southern Nuclear may make changes to the fire protection program without prior Commission approval only if the changes Renewed License No. DPR-57 Amendment No. 252
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow
< 10% rated core flow:
THERMAL POWER shall be *24% RTP.
2.1.1.2 With the reactor steam dome pressure > 785 psig and core flow
> 10% rated core flow:
MCPR shall be > 1.07 for two recirculation loop operation or > 1.09 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System (RCS) Pressure SL Reactor steam dome pressure shall be < 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed:
2.2.1 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.
2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.
2.2.3 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, the Vice President - Hatch and the off site review committee.
(continued)
HATCH UNIT 1 2.0-1 Amendment No. 252
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.2 SL Violations (continued) 2.2.4 .....itthin. 310 days,
,... * .. a Licenseue
.... , Report(LR LE.+D vento shall be Feersuant
-paredpuruan to 10 CFR 50.73. The LER shall be submitted to the NRC, the offsite review committee, the Plant Manager, and the Vice President - Hatch.
2.2.5 Operation of the unit shall not be resumed until authorized by the NRC.
HATCH UNIT 1 2.0-2 Amendment No. 252
Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The Vice President - Hatch shall provide direct executive oversight over all aspects of Plant Hatch.
5.1.2 The Plant Manager shall be responsible for overall unit operation and for delegation in writing of the succession of this responsibility during his absence.
Certain plant support functions shall also be the responsibility of the Site Support Manager.
5.1.3 The Plant Manager or his designee shall be responsible for the Radiological Environmental Monitoring Program and for the writing of the Annual Radiological Environmental Operating Report.
5.1.4 Each of the individuals in Specification 5.1.1 through Specification 5.1.3 is responsible for the accuracy of the procedures needed to implement his responsibilities.
5.1.5 A Senior Reactor Operator (SRO) shall be responsible for the control room command function. During any absence of the responsible SRO from the control room while either unit is in MODE 1, 2, or 3, an individual with an active SRO license shall be designated to assume the control room command function.
During any absence of the responsible SRO from the control room while both units are in MODE 4 or 5, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.
HATCH UNIT 1 5.0-1 Amendment No. 2 5 2
Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Orqianizations 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 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, including plant specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Plant Hatch Unit 1 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 - Hatch 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 total of three plant equipment operators (PEOs) for the two units is required in all conditions. At least one of the required PEOs shall be assigned to each reactor containing fuel.
(continued)
HATCH UNIT 1 5.0-2 Amendment No. 252
Organization 5.2 5.2 Organization 5.2.2 Unit Staff
- e. (continued)
Any deviation from the above guidelines shall be authorized by the Plant Manager or by 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 overtime shall be reviewed monthly by the Plant Manager or designee to ensure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.
- f. The Operations Manager shall hold an active or inactive SRO license.
- g. The Shift Technical Advisor (STA) shall provide advisory technical support to the shift supervisor 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.
HATCH UNIT 1 5.0-4 Amendment No. 252
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 - Hatch and Plant Manager, shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
HATCH UNIT 1 5.0-5 Amendment No. 252
Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals
,,,o,-,,*,,, ,; -g v u a ... and .. ,*,*.. ~hall,*,
s be established, ,mplemo,,e ,*e, and,'""
,,a, , ;*",
ne, 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, respectively.
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) and appropriate analyses or evaluations justifying the change(s), and
- 2. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by the onsite review committee and the approval of the Vice President - Hatch; 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 that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
(continued)
HATCH UNIT 1 5.0-7 Amendment No. 252
(6) Southern Nuclear, 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 license shah 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 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions' specified or Incorporated below:
(1) Maximum Power Level Southern Nuclear is authorized to operate the facility at steady state reactor core power levels not In excess of 2,804 megawatts thermal, in accordance with the conditions specified herein.
(2) Technical Specificatlons The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 196 are hereby incorporated in the renewed license. Southern Nuclear snan operate the facility In accordance with the Technical Specifications and the Environmental Protection Plan.
(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 license supported by a favorable evaluation by the Commission.
(a) Elre Protection Southern Nuclear shall Implement and maintain In effect all provisions of the fire protection program, which Is referenced Inthe the Updated Final Safety Analysis Report for the facility, as contained 2The original licensee authorized to possess, use, and operate the facility was Georgia Power Company (GPC). Consequently, certain historical references to GPC remain In certain license conditions.
Renewed Ucense No. NPF-5 Amendment No. 196
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1 .1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow
< 10% rated core flow:
THERMAL POWER shall be <24% RTP.
2.1.1.2 With the reactor steam dome pressure > 785 psig and core flow
> 10% rated core flow:
MCPR shall be > 1.08 for two recirculation loop operation or > 1.10 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System (RCS) Pressure SL Reactor steam dome pressure shall be < 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed:
2.2.1 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.
2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2'.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.
2.2.3 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, the Vice President - Hatch, and the offsite review committee.
(continued)
HATCH UNIT 2 2.0-1 Amendment No. 196
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.2 SL Violations (continued) 2.2.4 Within 30 days, a Licensee Event Report (LER) shall be prepared pursuant to 10 CFR 50.73. The LER shall be submitted to the NRC, the offsite review committee, the Plant Manager, and the Vice President - Hatch.
2.2.5 Operation of the unit shall not be resumed until authorized by the NRC.
HATCH UNIT 2 2.0-2 Amendment No. 196
Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.i .i The Vice President - Hatch sihall provide direct executive oversight over all aspects of Plant Hatch.
5.1.2 The Plant Manager shall be responsible for overall unit operation and for delegation in writing of the succession of this responsibility during his absence.
Certain plant support functions shall also be the responsibility of the Site Support Manager.
5.1.3 The Plant Manager or his designee shall be responsible for the Radiological Environmental Monitoring Program and for the writing of the Annual Radiological Environmental Operating Report.
5.1.4 Each of the individuals in Specification 5.1.1 through Specification 5.1.3 is responsible for the accuracy of the procedures needed to implement his responsibilities.
5.1.5 A Senior Reactor Operator (SRO) shall be responsible for the control room command function. During any absence of the responsible SRO from the control room while either unit is in MODE 1, 2, or 3, an individual with an active SRO license shall be designated to assume the control room command function.
During any absence of the responsible SRO from the control room while both units are in MODE 4 or 5, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.
HATCH UNIT 2 5.0-1 Amendment No. 196
Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Orqanizations 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 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, including plant specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Plant Hatch Unit 2 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 - Hatch 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 total of three plant equipment operators (PEOs) for the two units is required in all conditions. At least one of the required PEOs shall be assigned to each reactor containing fuel.
(continued)
HATCH UNIT 2 5.0-2 Amendment No. 196
Organization 5.2 5.2 Organization 5.2.2 Unit Staff
- e. (continued)
Any deviation from the above guidelines shall be authorized by the Plant Manager or by 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 overtime shall be reviewed monthly by the Plant Manager or designee to ensure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.
- f. The Operations Manager shall hold an active or inactive SRO license.
- g. The Shift Technical Advisor (STA) shall provide advisory technical support to the shift supervisor 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.
HATCH UNIT 2 5.0-4 Amendment No. 196
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 - Hatch and Plant Manager, shall meet or exceed the minimum qualifications of ANSI N18.1-1971 I for comparable positions, except for the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
HATCH UNIT 2 5.0-5 Amendment No. 196
Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The folloAi;ng prgrarmrso and manualos shall be establish ,-i immlImenfil and mari*torinnr 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, respectively.
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) and appropriate analyses or evaluations justifying the change(s), and
- 2. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.106, 40 CFR 190,10 CFR 50.36a, and 10 CFR 50, Appendix I, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by the onsite review committee and the approval of the Vice President - Hatch; 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 that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
(continued)
HATCH UNIT 2 5.0-7 Amendment No. 196