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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits ML17310A5211993-08-0505 August 1993 Proposed Tech Specs Requesting to Change Word Pressurizer to RCS for Item #4 in Both Tables 3.3-10 & 4.3-7 ML17310A5151993-08-0505 August 1993 Proposed Tech Specs Changing Surveillance Frequency from Monthly to Quarterly for Channel Functional Tests for RPS & ESFAS Instrumentation ML17310A4211993-06-30030 June 1993 Proposed Tech Specs Requesting Addl Operating Margin in Time Response of Turbine Driven AF Pump to SG Low Level Signal ML17310A2981993-05-20020 May 1993 Proposed TS 4.7.9 Re SR to Ensure Operability of Snubbers ML17306B2671993-01-25025 January 1993 Proposed Tech Specs,Reflecting Revised Train a Kw Value to Be Rejected & Load Designation & Incorporation of Provisions Discussed in 920508 Ltr Re DG Full Load Rejection Testing ML17306B1451992-11-20020 November 1992 Proposed Tech Specs Revising TS 3.2.1 Lhr, & TS 3.2.4, DNBR Margin, Increasing Action from 1 H to 4 H for COLSS Allowed Out of Svc Time Before Requirements Based on More Restrictive Core Protection Calculator Limits Apply ML17306A6491992-04-13013 April 1992 Proposed TS 3.4.8.3 Re RCS - Overpressure Protection Sys ML17306A4731992-02-14014 February 1992 Proposed Tech Specs Re Implementation of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent TS in Administrative Controls Section of TS & Relocation of Procedural Details of RETS to Odcm.... ML17306A4031992-01-16016 January 1992 Proposed Tech Specs Amend to TS Section 3.6.3,table 3.6-1 Deleting Type C Testing Requirements for Eight Valves ML17306A3701991-12-30030 December 1991 Proposed Tech Spec Table 6.2-1 Re Min Shift Crew Composition ML17306A3781991-12-30030 December 1991 Proposed Tech Spec Section 3.6.1.7 Re Containment Purge Supply & Exhaust Valves 1999-09-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A9451996-05-14014 May 1996 Rev 3 to Significant Condition Investigation. ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5691996-03-0505 March 1996 Revised Pages to ISI Program Summary Manual ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B3181995-12-20020 December 1995 Revised Pages to ISI Program Summary Manual ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17312A9381995-02-0303 February 1995 Corrective Action Program. ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0911994-03-0202 March 1994 SG Tube Insp Plan. ML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0251994-01-27027 January 1994 Unit 2 Steam Generator Tube Insp Plan Addendum. ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7421993-10-27027 October 1993 Revised Unit 1 SG Tube Insp Plan. ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6501993-09-17017 September 1993 Unit 1 SG Tube Insp Plan. ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits 1999-09-29
[Table view] |
Text
CONTROLLED BY USE}I ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP ISEG FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site.Each shall have a Bachelor's Degree in engineering or related science and at least two years professional level experien"e in his field.RESPONSIBILITIES 6.2.3.3 The ISEG shall be'responsible for maintaining surveillance of plant activities to provide independent verification" that these activities are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hazards.AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to the Director, Nuclear Safety and Licensing, Plant Manager, and the Manager, Nuclear Safety Group (NSG).RECORDS 6.2.3.5 Records of activities performed by the ISED shall be prepared, main-tained, and forwarded each calendar month to the Director, Nuclear Safety and Licensing.
6.2.4 SHIFT
TECHNICAL ADVISOR 6.2.4.1 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.The STA shall be onsite and shall be available in the control room within 1O minutes whenever one or more units are in MODE 1, 2, 3, or 4.6.3 UNIT STAFF UALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of AHS 3.1-1978 and Regulatory.
Guide 1.8, September 1975, except for the Radiation Protection and Chemistry Manager who shall meet or exceed the qualifi-cations of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a'scientific or engineering discipline with specific training in plant design and plant operating character-istics, including transients and accidents.
i+><g 7."Not responsible for sign-off function.PALO VERDE-UNIT.1'809i50i48 880'366 PDR ADOCK 05000528 P PNV'6-6 AMEHDMEHT HO-25 0 E INSERT An additional exception is that the Senior Reactor Operator (SRO)license requirement for the Operations Manager shall be met if either the Operations Manager or the Operations Supervisor holds a valid SRO license.The holder of the SRO license shall direct the licensed activities of the licensed operators.
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ONTROI LED BY USE ADMINISTRATIVE CONTROLS 6.2.3 IHDEPEHDENT SAFFTY ENGINEERING GROUP (ISEG)FUNCTION 6.2.3.l The.ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site.Each shall have a Bachelor's Degree in engineering or related science and at least two years professional level experience in his:: fi el d.RESPONSIBILITIES 6.2.3.3 The ISEG shall be r'esponsible for maintaining surveillance of plant activities to provide independent verificat'ion" that these activities are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hazards.AUTHORITY 6;2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to the Director, Nuclear Safety and Licensing, Plant Manager, and the Manager, Nuclear Safety Group (NSG).RECORDS 6.2;3.5 Records of activities performed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to the Director, Nuclear Safety and Licensing.
6.2.4 SHIFT-TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor (STA)shall provide advisory technical support to the Shift Supervisor in the areas of thermal.hydraulics, reactor engineering, and pl'ant analysis with regard to the safe operation of the unit The STA shall be onsite and shall be available in the control room within 10 minutes whenever one or more units are in MODE 1, 2, 3, or 4.6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of, the unit staff shall meet or exceed the minimum qualificat-ionss of ANS 3.1"1978 and Regulatory Guide 1.8, September 1975, except for the Radiation Protection and Chemistry Manager who shall meet or exceed the qualifi-cations of Regulatory Guide 1.8,'September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineeri'ng discipline with specific training in plant design and plant operating character-istics, includi'ng transients and accidents."Not responsible for sign-off function.PALO VERDE-UNIT 2 AMEHDMENT NO.14
~~INSERT An additional exception is that the Senior Reactor Operator (SRO)license requirement for the Operations Manager shall be met if either the Operations Manager or the Operations Supervisor holds a valid SRO license.The holder of the SRO license shall direct the licensed.activities of the licensed operators.
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~~ONTROLLED BY USEP'~~A ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP ISEG)FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site.Each shall have a Bachelor's Degree in engineering or related science and at least two years professional level experience in his field.RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification" that these activities are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hazards.AUTHORITY 6.2.3.4 The'SEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations a'ctivities or other~~~.-~~means of improving plant safety to the Director, Nuclear Safety and Licensing,-4" Plant Manager, and the Manager, Nuclear Safety Group (NSG).RECORDS 6.2.3.5 Records of activities performed by the ISEG shall be prepared, main-tained, and'forwarded each calendar month to the Director, Nuclear Safety and Licensing.
6.2.4 SHIFT
TECHNICAL ADVISOR 6.2.4.1 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.The STA shall be onsite and shall be available in the control room within 10 minutes whenever one or more units are in MODE 1, 2, 3, or 4.6.3 UNIT STAFF UALIFICATIONS
~6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANS 3.1-1978 and Regulatory Guide 1.8, September 1975, except for the Radiation Protection and Chemistry Manager who shall meet or exceed the qualifi-cations o'f Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineerin'g discipline with specific training in plant design and plant operating character-istics, including transients and accidents.
'g~E~>'ot responsible for.sign-off function.PALO VERDE-UNIT 3 6-6 INSERT An additional exception is that the Senior Reactor Operator (SRO)license requirement for the Operations Manager shall be met if either the Operations Manager or the Operations Supervisor holds a valid SRO license.The holder of the SRO license shall direct the licensed activities of the licensed operators.
C ATTACHMENT 2 1)Unit Operations Department Organization Chart 2)Position Summary for Operations Supervisor 4
OP ERAT I OjilS I"lANAGER OPEP,AT IOUS SUPER V I SOP,'V]OP.Vi CONTROL EVALUATORS;'ECRETARY L I CE('(SE CAIID IDATES SHIF I SUPEPVISnP SHIFT SUPERVISOR SHIFT SUPERVISOR SHIFT SUPERVISOR Sl IIFT-SUP EPV ISOP.SIIIF'I'UPLPVISnR ASS T.Sl llf T SUPV llUCL OPEP.A I ORS tlUCL OPEP.1ECH OPS SPT LEAD Of'S SPT TECH ASST.SHIFT SUPV I'IUCL OPERATORS l'IUCL OPER TECH OPS SPT f.EAD'PS SPT TECH ASST.SHIFT SUPV NUCL OPERATORS l'tUCL OPER TECf<OPS'SPT LEAD OPS SPT TECH ASST.SHIFT SUPV rlUCL OPERATORS NUCL OPEP.TECH OPS SPT LEAD OPS SPT TECH ASST.Sfl!FT SUPV riucL opERrnops NUCL OPER TECfl OPS SPT LE'AD OPS SPT"lECH ASST.Sfllr7 SUliV rIUCL or.ERA I Or'S,, HUE L OPFPj'1FCII Or S SPr l.rA'I.nPS Sr-r S Erll 4 V~t OPERATIONS SUPERVISOR The Operations Supervisor assists and acts as the principal alternate to the Operations Manager.He coordinates the activities and performance of the Shift Supervisors to ensure that the conduct of the operating staff is consistent with protection of the health and safety of the public and is in compliance with all applicable rules, regulations and procedures.
He ensures that identified plant deficiencies receive the appropriate work priority to maintain plant reliability.
He reviews various operating logs and records for accuracy, completeness, adherence to applicable administrative procedures, regulations and Technical Specifications, and to maintain current knowledge of plant activities.
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