Proposed Tech Specs Changing Responsibility for Review & Audit of App B Tech Specs Due to TVA Reorganization. Description & Justification for Changes & NSHC Determination EnclML20212R423 |
Person / Time |
---|
Site: |
Sequoyah ![Tennessee Valley Authority icon.png](/w/images/c/ce/Tennessee_Valley_Authority_icon.png) |
---|
Issue date: |
04/17/1987 |
---|
From: |
TENNESSEE VALLEY AUTHORITY |
---|
To: |
|
---|
Shared Package |
---|
ML20212R393 |
List: |
---|
References |
---|
NUDOCS 8704270169 |
Download: ML20212R423 (7) |
|
|
---|
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
I ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANCE SEQUOYAH NUCLEAR PLANT DOCKET NOS. 50-327, -328 (TVA SQN TS 87-05)
PROPOSED _ RESPONSIBILITY CHANGES TO SECTION 5.0, ADMINISTRATIVE CONTROLS, OF APPENDIX B LIST OF EFFECTED PAGES S-1 5-2 5-3 l
)
8704270169 B70417 PDR ADOCK 05000327 P PDR l
5-1 5.0 Adninistrative Controls 5.1 Responsibility
% 4. t h er- 3 The :t:0!;. ;g:rir.ter. der.t hr.s responsibility for operating the plant in compliance with these environmental technical specifications.
5.2 Review and Audit 5.2.1 Review LICEAfSEE The T7f 1,_' _;.., ZuTT is responsible for the review of procedures for meeting these environmental technical specifications.
The above nentioned review shall be conducted on the following:
A. Proposed changes to the Environmental Technical Specifications and evaluated impact of the change. , ,
, B. Proposed changes to station operating procedures, which affect the i
environmental effects of the station. .
l C. Proposed changes or nodifications to station or unit equipment, or systems which might have an environmental impact, in order to detemine the environmental impact of the change.
-em 9
5-2 D. All routine reports prior to their submittal to NRC (described in Subsection 5.4.1).
E. All nonroutine reporte prior to submittal of the written report (described in Subsections 5.4.2.a. b, and cl.
F. Investigations of all reported instances of noncompliance with Environ-mental Technica? Specifications, associated corrective actions, and measures taken to prevent recurrence.
5.2.2 Audit (LICEN.SEE)
The T,'.'A Of fi m .T tr belitj Anr== ;..d Audit St;ff shall conduct an Avtur opts /f' f,
[. ram. 7/vE PvotT6 5F44 88 CMDWT#O '
/NMf/AloENTLofYthe environmental monitoring 4 20 0l's prog??$P0tVS/84E fet: t.
of 'r/F /Nbt VfDV4L cR. lY/lf0A/MIA/(p T//f .S/fCIfIC AcTivi ry. l'ESut 5.3 Changes Ts & THf in Station AvoirorAcOoeration Design ri.n r/Fs .sydli (;f />toisrAwr4 ps:b MbiSV4ILAalF hlISWicried Changes in station design or operation may 6e made subject to the following conditions:
A.
The licensee may (1) make changes in the station design and operation, and (2) conduct tests and experiments not described in this document without prior Commission approval.,unless the proposed change, test or experirent involves a change in the objectives of the ETS and/or an unreviewed environmental question of significant impact.
B. A proposed change, test or experinent shall be deemed to involve an unreviewed enviromental question'if it concerns (1) a matter which may result in a significant increase in a,ny, adverse environmental impact
[l '
---. .-.,-n - ,. , - . . -,- , - m,
l 5-3
{
previously evaluated in the final environmental impact statement as modified by testimony to the Atomic Safety and Licensing Board, sur pienents thereto, environmentai impact appraisals, or in initial or
'inal adjudicatory decisions; cr (2; a ;ign'fi r.t d. , ' Offla;;t; G 2 .
- r;c le.;l = ;p;;if!J 2;
- ;;tiu 01.;G;G; ef 10 CT 01; or S 7 a matter not previously reviewed and evaluated in the documents specified in (1) of this section which may have a significant adverse environmental impact.
C. The licensee shall maintain records of changes in facility.desian or operation made pursuant to this subsection. The licensee shall also maintain records of tests and experiments carried out pursuant to O
tg' paragarph "A" of this subsection. These records shall include a written evaluation which provides the bases for the detemination that the change, test, or experiment does not involve an unreviewed environmental question of substantive impact or constitute a change jn the objectives !
of these ETS. The licensee shall furnish to the Comission, annually or at
. l such shorter intervals as may be specified in the license, a report contain-ing descriptions, analyses, interpretations, and evaluations of such changes, tests and experiments.
D. Changes in the special studies, if required in Section 4.2, which affect. -
sampling frequency, location, gear, or replication shall be reported to the NRC within 30 days after their implementation, unless otherwise reported in accordance with Subsection 5.4.2. These reports shall describe the
E ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION FOR RESPONSIBILITY CHANGES TO SECTION 5.0, ADMINISTRATIVE CONTROLS, OF APPENDIX B (TVA SQN TS 87-05)
Description of Change This change will revise parts of section 5.0, Administrative controls, of the Appendix B environmental technical specifications. The proposed changes will reflect the new title for the station superintendent and assign the.
responsibility for review and audit to the licensee, instead of a snecific licensee organization. The change will also extend the audit time interval from annual to once per 18 months and delete reference to a defunct section of the Code of Federal Regulations (CFR).
Reason for Change The changes to responsibility for review and audit and the correct title for the station superintendent are necessary to reflect correct titles as a result of the TVA reorganization. Relaxation of. the required time interval for environmental compliance auditing will relieve TVA of additional manpower requirements and the unnecessary burden that is required by the annual audit.
Section 5.3 of the Administrative Controls gives conditions which must be met when making changes to the station design or operation. One of the conditions precludes significant changes in effluents or power level in accordance with requirements in section 51.5(b)(2) of 10 CFR 51. These specific requirements have been deleted from the CFR and no longer need to be referenced in the technical specifications.
Justification for Change The proposed change is necessary due to a TVA reorganization that eliminated the TVA Regulatory Staff. This change will assign the responsibility for review of procedures to meet the environmental technical specifications to the licensee. Holding the licensee responsible for this review, instead of a specific TVA organization, will eliminate the need for future technical specifications changes as a result of further TVA organizational changes.
Additional changes in the TVA reorganization will give the Environmental Quality Staff (EQS) responsibility for nonradiological environmental compliance auditing at TVA's nuclear power plant sites. This responsibility is being shif ted from the Power Quality Assurance and Audit Staff. The Division of Quality Assurance will work closely with EQS to ensure a smooth transfer of responsibilities. As with the change in responsibility for review, this proposed change will assign the responsibility for audit to the licensee, apposed to a specific TVA organization. .,
INGen a a C The proposed change also requests an increase in the audit period from annual to once per 18 months. This request is based on EQS's audit experience at Sequoyah, Watts Bar, and Browns Ferry Nuclear Plants and over ')ur years of conducting environmental compliance audits at TVA's coal-fired steam plants, the hydro plants, the National Fertilizer Development Center, and many other facilities. EQS believes that environmental requirements at nuclear plants with respect to air, water, and solid and hazardous wastes are not appreciably different from those at other facilities, and that audits on an 18-month basis will provide manar,ement with the necessary information relative to the status of environmental compliance at the plant.
I _- --
General requirements for environmental impact statements, negative declarations, and impact appraisals have been deleted from the CFR due to a turnover of these responsibilities to the Environmental Protection Agency (EPA). In consideration of the provisions of tnw Clean Water Act (33 USC, Section 1251, et seq.) and in the interest of avoiding duplication of effort, the conditions and monitoring requirements related to water quality and aquatic biota are specified in the National Pollution Discharge Elimination System (NPDES) Permit No. TN 026450 issued by the United States EPA to TVA.
This permit authorizes TVA to discharge controlled waste water from Sequoyah units 1 and 2 into the Tennessee River.
, NRC will be relying on the NPDES permit for protection of the aquatic environment from nonradiological effluents. This is referenced in sections 3.0 and 4.0 of the Appendix B technical specifications.
we
.._y .m, ._m - -
3 __ _ , g. . , , - .y-- ,-,_-. .--- _ ,_ , - --, . ,w -y-,,_ _ _ . --, ,,, , - -
ENCLOSURE 3 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONS FOR RESPONSIBILITY CHANGES TO SECTION 5.0, ADMINISTRATIVE CONTROLS,.0F APPENDIX B (TVA SQN TS 87-05)
- 1. Is the probability of an occurrence or the consequences of an accident previously evaluated in the safety analysis report significantly increased?
No, the changes in responsibilities for review and audits in the environmental technical specifications will not prevent these jobs from being performed. This job function will still be performed by the licensee in a satisfactory manner in order to meet the requirements.
Extending the audit time interval to 18 months will still provide the necessary information relative to the status of environmental compliance.
- 2. Is the possibility for an accident of a new or different type than evaluated previously in the safety analysis report created?
No, the proposed changes to the environmental technical specifications do not present new or different safety concerns. These changes will ensure that the licensee is responsible for compliance of these specifications.
- 3. Is the margin of safety significantly reduced?
No, safety is not effected by the changes to the environmental technical specifications. These changes effect responsibility for review and audits and thus the margin of safety is unchanged.
l 1
l I
i 0656h m