ML082800020
| ML082800020 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Vogtle, Farley  |
| Issue date: | 10/07/2008 |
| From: | Martin R Plant Licensing Branch II |
| To: | Stinson L Southern Nuclear Operating Co |
| Martin, R E, NRR/DLPM, 301-415-1493 | |
| Shared Package | |
| ML082800015 | List: |
| References | |
| TAC MD8941, TAC MD8942, TAC MD8943, TAC MD8944, TAC MD8945 | |
| Download: ML082800020 (14) | |
Text
-4 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 179, are hereby incorporated in the renewed license.
Southern Nuclear shall op~rate the facility in accordance with the Technical Specifications.
(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 renewed license supported by a favorable evaluation by the Commission.
- a.
Southern Nuclear shall not operate the reactor in Operational Modes 1 and 2 with less than three reactor coolant pumps in operation..
- b.
Deleted per Amendment 13
- c.
Deleted per Amendment 2
- d.
Deleted per Amendment 2
- e.
Deleted per Amendment 152 Deleted per Amendment 2
- f.
Deleted per Amendment 158
- g.
Southern Nuclear shall maintain a secondary water chemistry monitoring program to inhibit steam generator tube degration.
This program shall include:
- 1)
Identification of a sampling schedule for the critical parameters and control points for these parameters;
- 2)
Identification of the procedures used to quantify parameters that are critical to control points;
- 3)
Identification of process sampling points;
- 4)
A procedure for the recording and management of data; 1::",10" I ""'Ilvl _ I Init 1 I
Renewed License No. NPF-2 Amendment No. 179
-3 (2)
Alabama Power Company, pursuant to Section 103 of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess but not operate the facility at the designated location in Houston County, Alabama in accordance with te procedures and limitations set forth iil this renewed licens~.
(3)
Southern Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time speCial nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)
Southern Nuclear, 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,
, ~ealed sources for reactor ins,trumentation and radiation monitoring equipment calibration, and'as fission detectors in amounts as required; (5)
Southern Nuclear, 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 calibration or associated with radioactive apparatus or components; and (6)
Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 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 Commissions's regUlations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and 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 2775 megawatts thermal.
(2)
Technical S'pecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 171,are hereby incorporated in the renewed license.
Southern Nuclear shall. operate the facility in accordance with the Technical Specifications.
Farley - unit 2 Renewed License No. NPF-S'
, Amendment No.
171
5.2 5.2.2 Organization 5.2 Organization Unit Staff (continued)
- 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 for the minimum shift compliment defined in Specifications 5.2.2.a and b and health physics technicians shall be reviewed and approved by the Plant Manager, his designee, or by higher levels of management.
Any deviation from the above guidelines for key maintenance personnel shall be reviewed and approved by the Maintenance Manager or his designee.
- f.
The Operations Manager or at least one Operations Superintendent shall hold an SRO license.
- g.
The Shift Technical Advisor (STA) shall proVide adVisory technical support to the responsible SRO 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. The same individual may fill this position for both units.
Farley Units 1 and 2 5.2-3 Amendment No.17g::Unit 1)
Amendment No.171(Unit 2)
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 - Farley and Plant Manager, shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in 10 CFR 55, except for (1) the senior individual in charge of Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. 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. The Operations Manager shall meet or exceed the above requirements except that Technical Specification 5.2.2.1 shall specify the requirements regarding the holding of an SRO license.
Farley Units 1 and 2 5.3-1 Amendment No.17~Unit 1)
Amendment No.17'Unit 2)
-4
. for sample analysIs or Instrument calibration. or associated with radioactive apparatus or components;.
, (6)
. Sou1hern Nuclear. pursuanllo the Act and 10 CFA Perts 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 10 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. Seclion 50.54 of Part 50. and Section 70.32 of Part 70; all appncable provlslonsof the Act and the rules.
regulalions, and orders of the CommissIon no~ or hereafter In eHeet; and the additional condItions speclfled or Incorporated below:
(1)
MaxImum Power level Southern Nuclear Is authorized 10 operate the facility at steady slale reactor cora power levets not In excess of 2804 megawatts thermat.
(2)
Technlcal Speclficstlons I
The Technical Speclflcatrons (Appendix A) and the Enviro.nmental '
Protection Plan (Appendix B). as revised through Amendment Ho. 260 are hereby Incorporated In.the renewed license. Southern Nuclear sha.lI operate the facility In accordance with the Technical Specifications and the Environmental Protection Plan.
The Survel11ance ReqUirement (SR) contained In the Technl.cal Specifications and fisted below. Is not required to be performed Immediately upon ImplementaUon of Amendment No. 195. The SR nsted below shan be succeSsfully demon'stratedprlor to the lime and conditIon specified:
SR 3.8.1.18 shan be successfully demonstrated at Its next reguJarJy scheduled performance (3) fire Protection Southern Nuclear shall Implement end melntaln 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 Ihe updated Fire Hazards AnalysIs and Fire Protection Program for Edwln J. Hatch Nuclear Plant Units 1 and 2. which was originally submitted by letter daled 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 Nf) 260
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 or at least one Operations Superintendent shall hold an 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. 260
5.3.1 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications Each member of the unit staff, including Vice President - Hatch and Plant Manager, shall either meet or exceed the minimum qualifications of ANSI N18.1 1971, or shall meet or exceed the minimum qualifications of the accredited program requirements for those positions stipulated in Enclosure 1 to letter NL-07 1925. The Operations Manager shall meet or exceed the above requirements except that Technical Specification 5.2.2.1 shall specify the requirements regarding the holding of an SRO license. The senior individual in charge of Health Physics shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
H~,TCH UNIT 1 5.0-5 Amendment No.260
.c.
- -r *
(6)
Southern Nuclear. pursuant to Ihe Act and 10 CFA 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 shaD be deemed to contain. and ~ subject to. the conditions specified In the follQwing CommissIon regulations In 10 CFA Chapter 1: Part 20, Section 30.34 of Part 30~ Section 40.41 of Part 40. Section 60.54 of Part 50; and Section 70.32 of Part 70; all' appncable provisions of the
. Act and the rules, regulations, 'and orders cif the CommIssion now or hereafter In eHect; and the additional condltlonsl specified or Incorporated below:
(1)
Maximum Power level Southern Nuclear Is authorized to operate the facRiIy at steady state reaclor core power levels not In excess of 2,604 megawatts thermal, In accordancewith the conditions specified herein.
(2)
Technical Specifications The TechnlC8;1 SpecfflcaUons (Appendix A) and the environmental Protection Plan (Appendix 8), as revised through Amendment No., 204 are hereby Incorporated In the renewed license. SoulhemNuclear shell operate the facDity In accordance with the Technical Specifications end the Environmental Protecllon Plan..
(3)
Additional Conditions The matters specUled In the following condlUons shall be completed to.
. the satlsfacllon ofthe CommIssIon withIn the stated tlme periods following the Issuance of the renewed license or within 100 operational restrictions Indicated. The removal of these conditions shaJl be made by an amendment to the license supported by a favorable evalustlon by lhe.
Commission.
(a)
Are protection Southern Nuclear,shaR Implement Bnd maintaIn In effect aU provlslons of the fire protection program, which Is referenced In the.
the Updated Final Safety Analysis Report 'or the faclDly, 85 contained 2'fhe original licensee authorized to possess, use, and operate the facility was Georgia Power Company (GPC). Consequently, certain hlstoricaf references 10 GPC remaIn In certain license conditions.
Renewed Ucense No. NPF*5 Amendment No. 204
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 or at least one Operations Superintendent shall hold an 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. 204
5.3.1 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications Each member of the unit staff, including Vice President - Hatch and Plant Manager, shall either meet or exceed the minimum qualifications of ANSI N18.1 1971, or shall meet or exceed the minimum qualifications of the accredited program requirements for those positions stipulated in Enclosure 1 to letter NL-07 1925. The Operations Manager shall meet or exceed the above requirements except that Technical Specification 5.2.2.1 shall specify the requirements regarding the holding of an SRO license. The senior individual in charge of Health Physics shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
HATCH UNIT 2 5.0-5 Amendment No. 204
- 4 (2)
Technical Specifications and Environmental Protection Plan*
The Technical Snc"ificatlons contained In Appendix.A. as revised through Amendment NO..153:'i1rid the Environmental Protection Plan contained in Appendix B,both of which. are attached hereto, are hereby incorporated into this license. SOuthern Nuclear shall operat~ the facility in accord~mc~ 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 (8)
DELETED (9)
DELETED (10) Mitigation Strategy license Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(a) Fire fighting respOnse strategy with th~ following elements:
- 1.
Pre-deflned coordinated fire response strategy and guidance
- 2.
Assessment of mutual aid fire fighting assets
- 3.
Designated staging areas for eqUipment and materials 4.*
Command and control "
- 5.
Trai.rilng of response personnel (b) Operations to mitigate fuel damage considering the following:
- 1.
Protection and use of personnel assets.
2.**
Communications
- 3.
Minimizing fire spread
- 4.
Procedures for implementing integrated fire response strategy
- 5.
Identification of readily-available pre-staged equipment
- 6.
Training on integrated fire response slrategy
- 7.
Spent fuel pool mitlgaticm measures (c)
Actions to minimize release to include consideration of;
- 1.
Water spray scrubbing
- 2. - Dose to onsite responders Amendment No. 153
- 4*
C.
This license shall be deemed to contain and Is sUbject to the conditions s.pecified In the Commission's regulations set forth in 10 CFR Chapter Iami'is sUbject to all applicable provisions of the Act and to the rules, (egulations. and orders of the Commission now or hereafter in effect, and is sUbject to the additional conditions spe~f1ed or Incorporated below.
(1) Maximum Power Level Southern Nuclear Is authorized to operate the facility at reactor core power levels not In excess of 3625.6 megawatts thermal (100 percent power) in accordance 'with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical SoecificatiClnSl::()ntalnedlnApP~l'ldix,Ai~~ r~v!~~~ through Amendment ~.134and the Environmental Protection Plan contained In Appendix 8, bqth of which are attached hereto, are hereby ir'!corporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
The Surveillance ReqUirements (SRs) contained in the Appendix A Technical 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 time '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 arpendment.
(3) Southern Nuclear Operating Company shall be capable of establishing containment hydrogEl" monitoring within 90 minutes of initi~tlng safety injection follOWing a 1055 of coolant accident.
(4) Mitigation Strategy License Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(a) Fire fighting response strategy with the following. elements:
- 1.
Pre-defined coordinated fire resllonse strategy and guidance 2
Assessment of mutLialald fire figtliing assets
- 3.
Designated staging areas for equipment and materials
- 4.
Command and control
- 5.
Training of respo~se personnel Amendment No.
134
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 or at least one Operations Superintendent shall hold an SAO 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)
Vogile Units 1 and 2 5.2-3 Amendment No15~Unit 1)
Amendment Noj~Unjt 2)
5.3.1 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 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'he;'requirements of the accredited program in lieu of the above. The Operations Manager shall meet or exceed the above requirements except that Technical Specification 5.2.2.1 shall specify the requirements regarding the holding of an SRO license.
Vogtle Units 1 and 2 5.3-1 Amendment No. (Unit 1) 153 ft,rnendment No. (Unit 2) 134