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| 4 JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATION This change revised the frequency for auditing the physical security plan to once per 12 months, and adds the requirement to audit the Safeguards Contingency Plan every 12 resnths. This change is being sub.nitted, as requested by the NRC by the October 30, 1982 letter n c,a D. G. Eisenhut to All Licensees, because of inconsistencies between the requirements of 10 CFR 73 40(d) and standard technical specifications. | | 4 JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATION This change revised the frequency for auditing the physical security plan to once per 12 months, and adds the requirement to audit the Safeguards Contingency Plan every 12 resnths. This change is being sub.nitted, as requested by the NRC by the {{letter dated|date=October 30, 1982|text=October 30, 1982 letter}} n c,a D. G. Eisenhut to All Licensees, because of inconsistencies between the requirements of 10 CFR 73 40(d) and standard technical specifications. |
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| . 'c . 1 JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATIONS This change revises the frequency for auditing the site radiological emergency plan to once per 12 months. This change is being submitted as requested by the October 30, 1982 letter from D. G. Eisenhut to All Licensees because of an inconsistency between CFR 50.54(t) and standard technical specifications. | | . 'c . 1 JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATIONS This change revises the frequency for auditing the site radiological emergency plan to once per 12 months. This change is being submitted as requested by the {{letter dated|date=October 30, 1982|text=October 30, 1982 letter}} from D. G. Eisenhut to All Licensees because of an inconsistency between CFR 50.54(t) and standard technical specifications. |
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Proposed Tech Specs Re Reassignment of Responsibility for Annual Mgt Directive Issuance,Physical Security Audit Frequency & Site Radiological Plan Rev FrequencyML20069D778 |
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Site: |
Sequoyah ![Tennessee Valley Authority icon.png](/w/images/c/ce/Tennessee_Valley_Authority_icon.png) |
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Issue date: |
03/15/1983 |
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From: |
TENNESSEE VALLEY AUTHORITY |
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To: |
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Shared Package |
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ML20069D771 |
List: |
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References |
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NUDOCS 8303180537 |
Download: ML20069D778 (13) |
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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] |
Text
. .* ,
ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT TVA-SQN-TS-40 CHANGE NO. 1 REASSIGNMENT OF RESPONSIBILITY FOR ISSUING THE ANNUAL MANAGEMENT DIRECTIVE OUTLINING CONTROL ROOM COMMAND e
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4 4
1
- ENCLOSURE 1 (Continued) i i .
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! PROPOSED TECHNICAL SPECIFICATIONS i
i t
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- l. TVA-SQN-TS-40
! CHANGE NO. 1 1
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i SEQUOYAH NUCLEAR PLANT l
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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY . .
6.1.1 The Plant Superintendent shall be responsible for overall unit operation 4 and shall delegate in writing the succession to this responsibility during his absence.
6.1. 2 The Chief, Radiological Hygiene. Branch, shall be responsible for implementing the radiological environmental program and dose calculations and projections as described in the Offsite Dose Calculation Manual (00CM). These responsibilities include performance of surveillance requirements listed in Table 6.1-1.
6.1.3 The Shift Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function. A management directive to this effect, signed by, the NUC PR. Division Director shall be reissued to all station personnel on an, annual basis.
6.2 ORGANIZATION ,
~
0FFSITE 6.2.1.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2-1.
6.2.1.2 The offsite organization for the radiological enviromental monitoring program and dose calculations shall be as shown in Figure 6.2-3.
UNIT STAFF 1
6.2.2 The Unit organization shall be as shown on Figure 6.2-2 and:
~
- a. Each on duty 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 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.
I
- SEQUOYAH - UNIT 1 6-l
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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY , f 6.1.1 The Plant Superintendent shall be responsible for overall unit operation and shall delegate in writing the succassion to this responsibility during his absence.
6.1. 2 The Chief, Radiological Hygiene Branch, shall be responsible for i
implementing the radiological environmental program and dose calculations and projections as described in the Offsite Dose Calculation Manual (ODCM). These responsibilities include performance of surveillance requirements listed in Table 6.1-1.
6.1.3 Tne Shift Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function. .A . management directive to this effect, signed by, the NUC PR. Division Director shall be reissued to all station personnel on an annual basis.
- 6. 2 ORGANIZATION .
0FFSITE 6.2.1.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2-1.
6.2.1.2 The offsite organization for the raciological enviromental monitoring program and dose calculations shall be as shown in Figure 6.2-3.
UNIT STAFF 6.2.2 The Unit organization shall be as shown on Figure 6.2-2_and:
1 -
- a. Each on duty 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 Control Rocm 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-l
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JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATION This change would relieve the General Manager from the requirement for signing the management directive. This change would allow the Director of TVA's Division of Nuclear Power to assign the responsibility for control room command at each nuclear plant. This change is not safety related but administrative in nature.
- s ENCLOSURE 2 .
SEQUOYAH NUCLEAR PLANT TVA-SQN-TS-40 CHANGE NO. 2 l
REVISION OF FREQUENCY TO AUDIT THE PHYSICAL SECURITY PLAN, AND THE ADDITION OF THE SAFEGUARDS CONTINGENCY PLAN AS AN AUDIT REQUIREMENT TO TS 6.5.2.8.e 7_y ,. ., y - + ,__s _y- - - _ , , _ . -
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. - = ,
ADMINISTRATIVE CONTROLS
- e. The Site Radiological Emergency Plan and implementing procedures at least once per 24 months. ,
- f. The Plant Physical Security Plan, the Safeguards Contingency Plan, and_ ,
implementing procedures at least once per 12 months.
~ ~ I
- g. Any other area of unit operation considered appropriate by the NSRB or the Manager of Power.
- h. The Facility Fire Protection P'rogram and implementing procedures at least once per 24 months.
- i. An independent fire protection and loss prevention program inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
J. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
- k. The radiological environmental monitoring program and the results thereof at least once per 12 months.
- 1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
- m. The PROCESS CONTROL PROGRAM and implementing procedures for l SOLIDIFICATION of radioactive wastes at least once per 24 months.
l .
- n. The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977
.at least once per 12 months.
5 AUTHORITY '
l 6.5.2.9 The NSRB shall report to and advise the Manager of Power on those l areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
RECORDS l
6.5.2.10 Records of NSRB activities shall be prepared, approved and distributed as indicated below:
- a. Minutes of each NSR8 meeting shall be prepared, approved and forwarded to the Manager of Power within 14 days following each meeting.
- b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be l prepared, approved and forwarded to the Manager of Power within l 14 days following completion of the review.
l SEQUOYAH - UNIT 2 6-l'5
- a. . . .. .
ADMINISTRATIVE CONTROLS
- e. The Site Radiological Emergency Plan and implementing procedures at least once per 24 months.
- f. The Plant Physical Se'curity Plan, the Safeguards Contingency Plan, and implementing procedures at least once per 12 months.
~
I
- g. Any other area' of unit operation considered appropriate by the NSRB or the Manager of Power.
- h. The Facility Fire Protection P'rogram and implementing procedures at least once per 24 months.
- i. An independent fire protection and loss prevention program inspectico and audit shall be performed annualry utilizing either qualified offsite licensee personnel or an outside fire protection firm.
J. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
- k. The radiological environmental monitoring program and the results thereof at least once per 12 months.
- 1. The OFFSITE DOSE CALCULATION . MANUAL and implementing procedures at-least once per 24 months.
- m. The PROCESS CONTROL PROGRAM and implementing procedures for SOLIDIFICATION of radioactive wastes at least once per 24 months.
- n. The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977
.at least once per 12 months.
I AUTHORITY 6.5.2.9 The NSRB shall report to and advise the Manager of Power on those areas of responsibility specified in Sections 6.5.2.7 and 5.5.2.8.
RECORDS 6.5.2.10 Records of NSRB activities shall be prepared, approved and distributed as indicated below:
- a. Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Manager of Power within 14 days following each meeting.
- b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Manager of Power within 14 days following completion of the review.
SEQUOYAH - UNIT 1 6-l'5
, e
4 JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATION This change revised the frequency for auditing the physical security plan to once per 12 months, and adds the requirement to audit the Safeguards Contingency Plan every 12 resnths. This change is being sub.nitted, as requested by the NRC by the October 30, 1982 letter n c,a D. G. Eisenhut to All Licensees, because of inconsistencies between the requirements of 10 CFR 73 40(d) and standard technical specifications.
1 i
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-. .- . - . . - -. . _ - . - _- ..-. _ _ . .. = __- - _
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ENCLOSURE 3 i
! SEQUOYAH NUCLEAR PLANT
't
- TVA-SQN-TS Il0 CHANGE NO. 3 l
REVISION OF FREQUENCY TO AUDIT THE SITE RADIOLOGICAL EMERGENCY PLAN s
l .
I I
t l
1 I
ADMINISTRATIVE CONTROLS
- e. The Site Radiological Emergency Plan and implementing procedures at
. least once per 12 months.
- f. The Plant Physical' Security Plan and implementing procedures a".
least once per 24 months.
- g. Any other area of unit operation considered appropriate by the NSRll or the Manager of Power.
- h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.
- i. An independent fire protection and loss prevention program inspection and audit shall be performed annually utilizing either qualified offsite ifcensee personnel or an outside fire protection firm.
- j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years,
- k. The radiological environmental monitoring program and the results thereof at least once per 12 months.
- 1. The OFFSITE DOSE CALCULATION . MANUAL and implementing procedures at least once per 24 months.
- m. The PROCESS CONTROL PROGRAM and implementing procedures for SOLIDIFICATION of radioactive wastes at least once per 24 months.
- n. 'The performance of activities required by the Quality Assurance Program ~to meet the criteria of Regulatory Guide 4.15, December 1977 at least once per 12 months. .
!- AUTHORITY .
i 6.5.2.9 The NSRB shall report to and advise the Manager of Power on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of NSRB activities shall be prepared, approved and distributed as indicated below:
I a. Minutes of each NSR8 meeting shall be prepared, approved and forwarded
! to the Manager of Power within 14 days following each meeting.
- b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be i
prepared, approved and forwarded to the Manager of Power within l 14 days following completion of the review.
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SEQUOYAH - UNIT 1 6-l'5 *
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- P ADMINISTRATIVE CONTROLS
- e. The Site Radiological Emergency Plan and implementing procedures at least once per 12 months. ,
- f. The Plant Physical Security Plan and implementing procedures at least once per 24 months.
- g. Any other area of unit operation considered appropriate by the NSRB or the Manager of Power.
- h. The Facility Fire Protection P'rogram and implementing procedures at least once per 24 months.
- i. An independent fire protection and loss prevention program inspection and audit shall be perfor.ved-annually utilizing either qualified offsite licensee personnel or an outside fire protection fire.
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- j. An inspection and audit of the fire protection and losr prevention prograin shall be performed by an outside qualified fire consultant '
at intervals no greater than 3 years. ,
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- k. The radiological environmental monitoring program and the esults thereoD at least once per 12 months.
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Ic The;dFF5ITEDOSECALCULATION.MANUALandimplementingprodduresat least,once per 24 months. ,-
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- m. ' The PROCESS CONTROL PROGRAM and implementing procedures for ,
SOLIDIFICATION of radioactive wastes at least once per 24 months,. -
"' ,, I a .- The performer,ce of activities required by the Quality Assurance /
~ Frogram ~to mitet 1 the' criteria of Regulatory Guide 4.15, Defembir 1977 ,
at least once per 12 months. - .
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n AUTHORITY y/
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6.5.2.9 Tha NSRB shall report to and advise the Manaaer~of'Po$eEon those areas of responsibility jpecified in Sections 6.5.2.7 .. o anJA.5.2.67, e ,5 j , js
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RECORDS // , -
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- 6 5.2.10 Records of NSRB activities shall be preW;Ipd; ?ppecyqd and dist t as indicated below
- e' y 3 n/ ' 7 .
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- a. Minutes 'of each NSR8 meeting.shalP be- prejared, aporoved and forwarded j to the Manager of Power witMnel,4 dap 'fo11'owing each meeting. g
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- b. Reports of retievs encommsed by Section4.5.2/7 above, shall be
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'ims , f prepared, approved and f6rwarded to the Manager.of Power within:' '
g >> 14 days foifowing complotion of=the review.' . < ,
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Sf0UOYAH - UNIT 2 ' T 6-15 y w - i , x v-. ,
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. 'c . 1 JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATIONS This change revises the frequency for auditing the site radiological emergency plan to once per 12 months. This change is being submitted as requested by the October 30, 1982 letter from D. G. Eisenhut to All Licensees because of an inconsistency between CFR 50.54(t) and standard technical specifications.
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