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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20212F4601999-09-23023 September 1999 Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively, Approving Request to Revise TSs to Allow Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20207A5781999-05-20020 May 1999 Errata to Amend 163 to OL DPR-79 on 931126.SR 4.1.1.1.1.d Was Inadvertently Omitted from Pp 3/4 1-1 of Unit 2 TS IA-97-261, Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal1997-03-0404 March 1997 Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal ML20211K5631997-03-0404 March 1997 Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal ML20196L5151988-06-24024 June 1988 Amends 73 & 65 to Licenses DPR-77 & DPR-79,respectively, Modifying Paragraph 2.E of Licenses to Require Compliance W/ Amended Physical Security Plan ML20149J9931988-02-17017 February 1988 Amends 68 & 60 to Licenses DPR-77 & DPR-79,respectively, Revising Tech Spec Surveillance Requirements 4.7.7.e.3 to Allow Up to 1000 Cubic Ft Per Minute Intake of Air During Operation of Control Room Emergency Ventilation Sys ML20147E1631988-01-0707 January 1988 Amends 64 & 56 to Licenses DPR-77 & DPR-79,respectively, Changing Tech Specs to Increase Diesel Generator Continuous & 2 H Ratings in Surveillance Requirements ML20236F5241987-10-22022 October 1987 Amends 61 & 53 to Licenses DPR-77 & DPR-79,respectively, Deleting Three Categories of motor-operated Valves from Tech Spec Table 3.8-2 1999-09-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217F9551999-10-14014 October 1999 Application for Amends to Licenses DPR-77 & DPR-79,proposing Change to TS SRs & Bases to Incorporate ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plant Intersections ML20217E4211999-10-12012 October 1999 TS Change 99-15 to Licenses DPR-77 & DPR-79,providing Unisolation of Containment Penetrations Under Administrative Controls ML20212F4601999-09-23023 September 1999 Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively, Approving Request to Revise TSs to Allow Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20211K1521999-08-30030 August 1999 TS Change 99-10 to Licenses DPR-77 & DPR-79,providing Clarification to Current TS Requirements for Containment Isolation Valves ML20211M7261999-08-30030 August 1999 TS Change 99-08,for Amends to Licenses DPR-77 & DPR-79 to Provide Alternative to Requirement of Actually Measuring Response times.Marked-up & Revised TS Pages,Encl ML20209B7661999-06-30030 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,updating Current TS Requirements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196G4441999-06-24024 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,to Revise TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196F2121999-06-24024 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,to Change TS Allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20195E9661999-06-0707 June 1999 Application for Amend to License DPR-79,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 ML20207A5781999-05-20020 May 1999 Errata to Amend 163 to OL DPR-79 on 931126.SR 4.1.1.1.1.d Was Inadvertently Omitted from Pp 3/4 1-1 of Unit 2 TS ML20206E1341999-04-29029 April 1999 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change Request 99-03, Main Control Room Emergency Ventilation Sys Verses Radiation Monitors. Change Adds LCOs 3.3.3.1 & 3.7.7 & NUREG-1431 Changes ML20206E1551999-04-29029 April 1999 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 99-04, Auxiliary Feedwater Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20204H3991999-03-19019 March 1999 TS Change 99-01 to Licenses DPR-77 & DPR-79,relocating TS Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D5941999-02-26026 February 1999 Application for Amend to Licenses DPR-77 & DPR-79,relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6251999-02-26026 February 1999 Application for Amends to Licenses DPR-77 & DPR-79,revising TS to Provide for Consistency When Exiting Action Statements Associated with EDG Sets ML20206S0061999-01-15015 January 1999 TS Change 98-09 for Licenses DPR-77 & DPR-79,relocating TS 3.3.3.3, Seismic Instrumentation & Associated Bases from TS to Plant Technical Requirements Manual ML20199K5841999-01-15015 January 1999 Application for Amends to Licenses DPR-77 & DPR-79,adding New Action Statement to TS 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 Protection ML20195H6041998-11-16016 November 1998 Application for Amends to Licenses DPR-77 & DPR-79,revising EDG SRs by Adding Note to Allow SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Lockout Features ML20154H7201998-10-0808 October 1998 Supplemental Application for Amends to Licenses DPR-77 & DPR-79,changing TS to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1051998-08-27027 August 1998 Application for Amend to License DPR-79,revising TS to Provide for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F2981998-08-27027 August 1998 Revised Applications for Amends to Licenses DPR-77 & DPR-79, 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 Edg.Response to RAI Included in Encl ML20249C6321998-06-26026 June 1998 Application for Amends to Licenses DPR-77 & DPR-79,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 ML20248E9841998-05-28028 May 1998 Suppl TS Change 95-19 to Licenses DPR-77 & DPR-79,replacing Direct Ref to Nuclear QA Plan in TS Section 6.3.1,facility Staff Qualification,W/Actual Requirements Stated in TVA-NQA-PLN89-A ML20217N3411998-04-30030 April 1998 Application for Amends to Licenses DPR-77 & DPR-79,modifying TS 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 ML20203J1511998-02-25025 February 1998 Application for Amends to Licenses DPR-77 & DPR-79 to Change TS for Units 1 & 2,revising EDG Surveillance Requirements ML20202J6601998-02-13013 February 1998 Application for Amends to Licenses DPR-77 & DPR-79, Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7421998-02-13013 February 1998 TS Change 97-04 to Application for Amends to Licenses DPR-77 & DPR-79,relocating Snubber Requirements from Section 3.7.9 of TS to Plant Technical Requirements Manual ML20202J7101998-02-13013 February 1998 Application for Amends to Licenses DPR-77 & DPR-79,adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20198T4211998-01-21021 January 1998 Suppl TS Change 95-19 to Licenses DPR-77 & DPR-79,revising Title for President,Tva Nuclear & Chief Nuclear Officer to Generic Title of Chief Nuclear Officer ML20199K4441997-11-21021 November 1997 Application for Amend to License DPR-55,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 ML20211A3091997-09-17017 September 1997 TS Change 97-02 to Licenses DPR-77 & DPR-79,revising Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20137C8271997-03-19019 March 1997 Revised TS Change 96-01 to Licenses DPR-77 & DPR-79,revising Appropriate Specifications,Surveillances & Bases to Allow for Conversion from Westinghouse Fuel to Framatome Cogema Fuel ML20136J0251997-03-13013 March 1997 Application for Amends to Licenses DPR-77 & DPR-79,revising Allowed Enrichment of Fuel in TS Section 5.6.1.2 for New Fuel Pit Storage Racks from 4.5 to 5.0 Weight % U-235 IA-97-261, Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal1997-03-0404 March 1997 Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal ML20211K5631997-03-0404 March 1997 Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal ML20129D2561996-10-18018 October 1996 Application for Amends to Licenses DPR-77 & DPR-79,removing Existing Footnotes That Limit Application of Apc for Plant SG Tubes to Cycle 8 Operation for Both Units ML20129G7111996-09-26026 September 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising Fire Protection License Conditions & Relocation of Fire Protection Tech Spec ML20113G2421996-09-20020 September 1996 Application for Amends to Licenses DPR-77 & DPR-79, Clarifying Work Shift Durations for Overtime Limits ML20117J3341996-08-28028 August 1996 Application for Amends to Licenses DPR-77 & DPR-79, Revising Psv & MSSV Setpoint Tolerance from Plus or Minus 1% to Plus or Minus 3% ML20117D0921996-08-22022 August 1996 Application for Amends to Licenses DPR-77 & 79 Changing Tss of Sqb Units 1 & 2 by Deleting Table 4.8-1, DG Reliability & Revising Sectio 3.8.1 to Allow a Once Per 18 Month 7 Day AOT for EDGs ML20117D2931996-08-21021 August 1996 TS Change 96-03 to Licenses DPR-77 & DPR-79,revising TS 3.7.1.3, Condensate Storage Tank, to Include New Mode of Applicability to Read Mode 4 When SG Relied Upon for Heat Removal ML20117D3271996-08-21021 August 1996 TS Change 96-06 to Licenses DPR-77 & DPR-79,removing Surveillance Requirement 4.8.1.1.1.b to Verify Ability to Transfer Unit Power Supply from Unit Generator Supported Circuit to Preferred Power Circuit ML20112H0361996-06-0707 June 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of STSs ML20101N6981996-04-0404 April 1996 TS Change 96-01 to Licenses DPR-77 & DPR-79,allowing Use of Nuclear Fuel Provided by Framatome Cogema Fuels (Fcf). Proprietary & Nonproprietary Versions of Fcf TR Supporting TS Change 96-01 Encl.Proprietary Version of TR Withheld ML20096B3671996-01-0404 January 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising TS Change 95-22,extending Radiation Monitoring Instrumentation Surveillance Period Per GL 93-05 ML20095F0271995-12-12012 December 1995 Application for Amend to License DPR-79,consisting of TS Change 95-23 Revising TS SRs & Bases to Incorporate Alternate S/G Tube Plugging Criteria at Tube Support Plate Intersections,Per GL 95-05 ML20095D5431995-12-0808 December 1995 Application for Amend to Licenses DPR-77 & DPR-79,consisting of TS Change 93-09,revising Setpoints & Time Delays for AFW loss-of-power & 6.9 Kv Shutdown Board loss-of-voltage & degraded-voltage Instrumentation ML20095D5731995-12-0808 December 1995 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 95-20,extending Containment Spray & RHR Sys Nozzles Testing Period from 5 to 10 Yrs in Accordance W/Gl 93-05 ML20095D5811995-12-0808 December 1995 Application for Amend to Licenses DPR-77 & DPR-79,revising TSs to Implement Recent Rule Change to 10CFR50,App J ML20092E0191995-09-11011 September 1995 Application for Amend to License DPR-79,consisting of TS Change Request 95-13,rev 1 Re Extension of Response Time Surveillance Requirements for Unit Two Cycle 7 1999-09-23
[Table view] |
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.' / UNITED STATES o,,
!" o NUCLEAR REGULATORY COMMISSION f ,1 WASHINGTON, D. C. 20606 June 24, 1988 t
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENOMENT TO FACILITY OPERATING LICENSE Amen cent No. 73 License No. OPR-77
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- 1. The Nuclear Regulatory Commission (the Comission) has found that:
A. The application for amendment by Termessee Valley Authority (the licensee) dated September 15 and November 23, 1987, complies with the standard and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l
Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be l
conducted in compliance with the Comission's regulations; i
D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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- 2. Accordingly, paragraph C.E of Facility Operating License No. OPR-77 is hereby amended to read as follows:
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard trainir.g and qualification, and safeguards contingency plant including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements resisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10CFR50.54(p). The Safeguards Contingency Plan is incorporated into the Physical Security Plan. The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Sequoyah Physical Security Plan," with revisions submitted through November 23, 1987; and "Sequoyah Security Personnel Training and Qualification Plan," with revisions submitted through April 16, 1987.
Changes made in accordarce with 10 CFR 73.55.shall be implemented in accordance with the schedule set forth therein.
- 3. This license amendment is effective as of its date of issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION ry:-
uza ne B c, ssistant Director for Projects TVA Projects Division Office of Special Projects l Date of Issuance: June 24, 1988 l
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ATTACHMENT TO LICENSE AMENOMENT N0. 73 FACiLITYOPERATINGLICENSENO.OPR-77 DOCKET NO. 50-327
- Revise the License by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contains marginal lines indicating the area of change.
REMOVE INSERT License Page 12 License Page 12 s
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t i J. Relief and Safety Valve Test Requirements (Section 22.3, II.D.1)
TVA shall confom to the results of the EPRI test program. TVA shall provide documentation for qualifying (a) reactor coolant sys tem relief and safety valves, (b) piping and supports, and (c) block valves in accordance with the review schedule given in SECY-81-491 as approved by the Comission.
2.C.(24) Compliance with Regulatory Guide 1.97 TVA shall implement modifications necessary to comply with Revision 2 of Regulatory Guide 1.97, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Con-ditions During and Following an Accident," dated December 1980 by startup from the Unit 2 Cycle 4 refueling outage. ?
D. Exemptions from certain requirements of Appendices G and J to 10 CFR Part 50 are describeri in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement N .1. These exemptions are authorized by law and will not endanger life or property or the comon defense and security and are otherwise'in the public interest. The exemptions are, theref6re, hereby granted ~. The granting of these exemptions was authorized with 3e L issuance of the License for fuel Loading and Low Power Testing, dated February 29, 1980. The facility will operate, to the extent authorized here in conformity with the application, as amended, the provisions of the i
Act, and the regulations of the Comission.
2.E. Physical Protection
.The licensee shall fully implement and maintain in effect all l
provisions of the Comission-approved physical security, guard treining and qualification, and safeguards continaency plans including amendments mada pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55
($1 FR 27817 and 27822) and to the ' authority of 10 CFR 50.90 and 10CFR50.54(p). The Safeguards Contingency Plan is incorporated into the Physical Security Plan. The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Sequoyah Physical Security Plan," with revisions submitted through l November 23, 1987; and "Sequoyah Security Personnel Training and l
l Qualification Plan," with revisions submitted through April 16, 1987.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
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$2 :eou, UNITED STATES
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' 8 o NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20666 5 g June 24, 1988 4, + . . . . s/
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-79 i
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Tennessee Valley Authority (the licensee) dated September 15 and November 23, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of th' Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and l safety of the public, and (ii) that such activities will be i conducted in compliance with the Commission's regulations; l
- 0. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and l
i i E. The issuance of this amendment is in accordance with 10 CFR Part 51 I of the Commission's regulations and'all applicable requirements have been satisfied.
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- 2. Accordingly, paragraph 2.E of Facility Operating License No. OPR-79 is hereby amended .) read as follows:
The licensee shall fully implement and maintain in effect all l I
provisions of the Cmunission-apprcved physical security, guard training and qualification, and safequards contingency plans including amendnunts made pursuant to provisions of the Miscellaneous ;
Amendments and Search Requirements revisison to 10 CFR 73.55 (51 FR 21817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Safeguards Contingency Plan is incorporated i into the Physical Security Plan. The plans, which contain Safeguards !
Information protected under 10 CFR 73.21, are entitled: "Sequoyah Physical Security Plan," with revisions submitted through November 23, 1987; and "Sequoyah Security Personnel Training an(
Qualificaton Plan," with revisions submitted through April 16, 1 Changes made in accordance with 10 CFR 73.55 shall be implemente in accordance with the schedule set forth therein.
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION gf,,_ Suzanne c, sistant rector p for Projects TVA Projects Division Office of Special Projects l
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Date of Issuance: June P4, 1988 l
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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 65 FACILITY OPERATING LICENSE NO. OPR-79 00CKET NO. 50-328 Revise the License by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contains marginal lines indicating the are of change.
REMOVE INSERT License Page 11 License Page 11 i
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- s. Primary Coolant Outside Containment (Section 22.2, III.O.1)
Prior to exceeding 5 percent-power level, TVA is required to complete the leak tests on Unit 2, and results are to be sub-mitted within 30 days from the completion of the testing.
D. ' Exemptions from certain requirements of Appendices G and J to 10 CFR Part 50 are described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplerents No 1 and No 5. These exemptions are authorized by law and will not endanger life or property or the comon defense and security and are otherwise in the public interest. Therefore, these exemptions are hereby granted. The faci.'ity wil operate, to the extent authorized herein, in conformity with the application, as amended, the provision of the Act, and the regulation of the Comission A temporary exemption from General Design Criterion 57 found in Appendix A to 10 CFR Part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement No. 5, Section 6.2.4. This exemption is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest. The exemption, i.herefore, is hereby granted and shall remain in effect through the first refueling outage as discussed in Section 6.2.4 of Supplement 5 to the Safety Evaluation Report. The granting of the exemption is authorized with the issuance of the Facility Operating License. The facility will operate, to the extent authorized herein, in confomity wii:h the application as amended, the provisions of the Act, and the regulations of the Comission.
E. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Comission-approved physical security, guard training and qualification, and safequards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisison to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10CFR50.54(p). The Safeguards Contingency Plan is incorporated into the Physical Security Plan. The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Sequoyah.
Physical Security Plan," with revisions submitted through November 23, 1987; and "Sequoyah Security Personnel Training and Qualificaton Plan," with revisions submitted through April 16, 1987.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance wita the schedule set forth therein.
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