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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20113G2691996-09-20020 September 1996 Proposed Tech Specs Change 96-09, Clarification of Work Shift Durations for Overtime Limits ML20117J3391996-08-28028 August 1996 Proposed Tech Specs Revising Psv & MSSV Setpoint Tolerance from Plus or Minus 1% to Plus or Minus 3% ML20117D1651996-08-22022 August 1996 Proposed Tech Specs of SQN Units 1 & 2,deleting Table 4.8.1, DG Reliability, & Revising Section 3.8.1 to Allow Once Per 18 month,7 Day AOT for EDGs ML20117D3121996-08-22022 August 1996 Proposed Tech Specs,Lowering Minimum TS ice-basket Weight of 1,155 Lbs to 1,071 Lbs.Reduced Overall Ice Weight from 2,245,320 Lbs to 2,082,024 Lbs ML20117D3141996-08-21021 August 1996 Proposed TS 3.7.1.3 Re Condensate Storage Tank ML20117D3341996-08-21021 August 1996 Proposed Tech Specs Re Deletion of Surveillance Requirement 4.8.1.1.1.b ML20112H0431996-06-0707 June 1996 Proposed Tech Specs,Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of STSs ML20101N7071996-04-0404 April 1996 Proposed Tech Specs,Allowing Conversion from Westinghouse Fuel to Fuel Provided by Framatome Cogema Fuels ML20096B3761996-01-0404 January 1996 Proposed Tech Specs Extending Radiation Monitoring Instrumentation Surveillance Period Per GL 93-05 ML20096C2481996-01-0303 January 1996 Proposed Tech Specs,Revising Bases Section 3/4.7.1.2 to Indicate Current Operational Functions of turbine-driven AFW Level Control Valves Modified During Unit 1 Cycle 7 Refueling Outage 1999-08-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program 1999-08-30
[Table view] |
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ENCLOSURE 1 TENNESSEE VALLEY AUTkORITY SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 1 and 2 DOCKET NOS 327 AND 328 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS 95-19, SUPPLEMENT 1 DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGE I. DESCRIPTION OF THE PROPOSED CHANGE This change will revise the title of President, TVA Nuclear and Chief Nuclear Officer to Chief Nuclear Officer in proposed Section 6.1.3 and Section 6.2.1.b of the SON TS.
This change revises this title throughout the SON TSs.
II. REASON FOR THE PROPOSED CHANGE The current TVA title for the position that is responsible for the associated TS requirements is Chief Nuclear Officer and Executive Vice President, TVA Nuclear. The proposed change will revise the TS title to a more generic title of Chief Nuclear Officer. The proposed title will be consistent with the current TVA title and should be compatible with future title changes for this position each that subsequent TS amendments will be minimized.
III. SAFETY ANALYSIS The proposed supplemental change is an administrative title change that does not affect the implementation of TS requirements. The position that is responsible at the corporate level for safe operation and overall nuclear safety of the TVA plants has not changed. Therefore, this administrative title change will not adversely affect nuclear safety.
9001270054 900121 PDR ADOCK 05000327 p PDR _
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. ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY SEQUOYAH PLANT (SQN)
UNITS 1 and 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS 95-19 SUPPLEMENT 1 MARKED PAGES I. AFFECTED PAGE LIST Unit 1 6-1 Unit 2 6-1 II. MARKED PAGES See attached.
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6.0 ADMINISTRA 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and R62 shall delegate in writing the succession to this responsibility during his absence.
R182 6.1.2 The Shift Operations Supervisor (or during his absence from the Control Room, a designated individual) shall be res >onsible for the Control Room coe-1r dn h$ b e a o r n a a /
onusrx 6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS An onsite and an offsite organization shall be established for unit operation g78 and corporate managtment. The onsite and offsite organization shall include the positions for activities affecting the safety of the nucle.r power plant. .
M i j a. Lines of authority, responsibility, and communication shall be estab-Ii5 lished and defined from th'e highest management levels inrough inter-
] mediate levels to and including all operating organization positions.
t A t [, These relationships shall be documented and updated, as appropriate, g\ in the form of organizational charts, functional descriptions of i departmental responsibilities and relationships, and job descriptions
} for key personnel positions, or in equivalent forms of documentation, y .These requirements shall be documented in thelf5AR4pd Vi1Yba[
O lupgage
, tVacptrptcyw1pi pr CyR 56.7)Te}Q }f 4EcmcNTS $
gL b. The !dpZ%1ef Nuclear Officer shall have corporate responsibi Tty for overall plant nuclear safety. This 3 individual shall take any measures needed to ensure acceptable perfom g7g
$ ance of the staff in ope ating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.
J a $ c. The Plant Manager shall be responsible for overall unit safe operation o( and shall have control over those onsite resources necessary for safe skp operation and maintenance of the plant,
- d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appro-priate onsite manager; however, they shall have sufficient organiza-tional freedom to ensure their independence from operating pressures.
6.2.2 FACfLITYSTAFF
- a. Each on-duty unit shift shall be composed of at least the miniinum shift crew composition shown in Table 6.2-1.
- b. At least one licensed Reactor Operator shall be in the unit Control Room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.
October 2, 1995 6-1 Amendment No. 32, 58, 74, 152, 178, 212 SEQUOYAH - UNIT 1
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Cf As 7-VA W DMINISTRATIVE CONT -
6.1 ' RESPONSIBILITY The Plant Manager shall be responsible for overall unit operation and R50 6.1.1 shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shift Operations Supervisor (or during his absence from the Control lR169 Room, a designated individual) shall be restonsible for the Control Rone er=-
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r i Dc.wi W6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS An onsite and an offsite organization shall be established for unit operation R66 7 d corporate management. The onsite and offsite organization shall include .
o t posicions for activities affecting the safety of the nuclear power plant.
CM A a. Lines of authority, responsibility, and connunication shall be estab-t lished and defined from the highest management levels through inter-s A mediate levels to and including all operating organization positions.
gk These relationships shall be documented and updated, as appropriate, in the fom of organizational charts, functional descriptions of I {A g g3 departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms _of documentation.
Ds These requirements shall be documented in th ffS&E and yflMed L Luppv0/n,stcgrupteA1thA C5R kW.JT(eM SumcMwr .i
/ g2k2 W,hief Nuclear Officer shall have
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% [b. The corporate responsTETihMyerall plant nuclear safety'. This individual shall take any measures needed to ensure acceptable R66 A V performance of the staff in operating, maintaining, and providing hJ a3 technical support in the plant so that continued nuclear safety is
" tt assured.
$ c. The Plant Manager shall be responsible for overall unit safe opera-tion, and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.
- d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 FACILITY STAFF
- a. Each on duty unit shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
- b. At least one licensed Reactor Operator shall be in the unit Control Room when fuel is in the reactor.
In addition, while the unit is in D; .
MODE 1, 2, 3 c- 4, at least one licensed Senior Reactor Operator shall be in the Control Room.
October 2, 1995 6-1 Amendment No. 24, 50, 66, 142, 169, 202 SEQUOYAH - UNIT 2
1
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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 1 and 2 PROPOSED TECHNICAL SPECIFICATION' (TC) CHANGE TS 95-19 i SUPPLEMENT 1 REVISED PAGES I. AFFECTED PAGE LIST Unit]
6-1 hit 2 6-1 II. REVISED PAGES See attached.
E3-1
6.0 ADMINISTRATIVE CONTROLS 6,1 R'ESPONSIBILITY 6.1.1 The plant Manager shall be responsible for overall unit operation and R62 shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shif t Operations Supervisor (or during his absence f rom the Control Room, a designated individual) shall be responsible for the Control Root command function.
6.1.3 The Chief Nuclear Officer is responsible for the safe operation of all TVA Nuclear Power Plants.
1 6.2 ORGANIZATION l 6.2.1 0FFBITE 7JH) ONDITE ORGANIZATIONS An onsite and an offsite organization shall be established for unit operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuc5 ear power plant.
- a. bines of authority, responsibility, and communicatzon shall be established and defined from the highest management levels through ,
intermediate levein to and including all operating organization positions. These eglationships shall be documented and updated, as R78 appropriate, in the form of organizational 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 *.he Nuclear Power Organization Topical Report (TVA NPOD89-A).
- b. The Chief Nuclear Officer shall have corporate responsibility for overall plant nuclear safety. This individual shall take any measures needed to ensure acceptable performance of the staff in llR216 operating, naintaining, and providing technical support in the plant l so tnat continued nuclear safety is assured.
- u. The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite resources R78 nacssaary for safe operation and mainteaance of the plant.
- d. '." individuals who train the operating staff and those who carry out r health physics and quality assurance functions may report to the '
appropriate onJite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 FACILITT,STAPP
- a. Each on-duty unit shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
- b. At least one licensed Reactor Operator shall be in the unit Control Room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3 oJ 4, at least one licensed Senior Reactor Operator shall be in the Control Room.
SEQUOYAH - UNIT 1 61 Amendment No. 32, 58, 74, 152, 178, 212,
. - _ . - -- . . . - _ _ . _ ~ - _ - - - . - - - .- - . - - . _ . - _ _ .
- 6.0 ADMINISTRATIVE CONTROLS 6.1 PESPONSIBILITT 6.1.1 The Plant Manager shall be responsible for overall unit operation and RF0 shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shif t Operations Superviso. (or during his absence from the control. iR169 Room, a designated individual) shall be responsible for the Control Room command function.
6.1.3 The Chief Nuclear Of ficer is responsible f ar the safe operation of all .
TVA Nuclear Power Plants. !
6.2 ORGANIZATIOH 6.2.1 OFFSITE_AND ONSITE ORGANIZATIONS An onsite and an offsite organization shall be established tot unit operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant. I
- a. Lines of authority, responsibility, and communication shs11-be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be doctmented and updated, as appropriate, in the form of organizational charts, functional R66 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 Nuclear Power Organization Topical Report (TVA-NPGsB9-A).
- b. The Chief Nuclear Officer shall have corporate responsibility for overall plant nuclear safety. This individual shall take any lR202 measures needed to ensure acceptable perforwance of the staf f in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.
- c. The Plant Manager shall be responsible for overall unit safe operation, and shall have control over those onsite resources R66 necessary for safe operation and maintenance of the plant,
- d. The individuals who train the aperating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite managers however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 FACILITY STAFF
- a. Each on duty unit shif t shrJ1 be composed of at least the minimum shift crew composition shown in Table 6.2 1.
- b. At least one licensed Reactor Operator shall be in the unit Control Room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the control Room.
-SEQUOYAH - UNIT 2 6-1 Amendment Nos. 24, 50, 66, 142, 1F9. 202,
, . . . _. -- = . - . . - . ... - ._ - _- -.- - - - - ..-...--- ..-
ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY SEQUOYAN NUCLEAR PLANT (SQN) i UNITS 1 and 2 .
PROPOSED TECNNICAL SPECIFICATION (TS) CHANGE TS 95-19 )
SUPPLEMENT 1 l COMITNENT DESCRIPTION d
The next revision of the Nuclear Quality Tssurance Plan will ,
reflect the new positiota title and provide a general update description of the-nuclear organization. The target date for submittal of this revision to NRC is 14 arch 31, 1998.
-E4-1=
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