Letter Sequence Response to RAI |
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MONTHYEARML20115H4711996-07-17017 July 1996 Forwards Response to RAI in NRC Ltr to Util Dtd 960327, RAI - Reliability of Offsite Power Study - Sequoyah Nuclear Plant,Units 1 & 2. Justifications That Voltage at Safety Buses Will Not Go Below 5220 Volts,Included Project stage: Response to RAI ML20133L1121997-01-17017 January 1997 Forwards RAI Re Reliability of Offsite Power Grid at Plant. Requested Info Should Be Provided by Licensee within 60 Days of Receipt of Ltr Project stage: RAI ML20140C5921997-06-0202 June 1997 Forwards Response to 970117 RAI Re Details on Analysis That Evaluates Adequacy of Offsite Power Sys.Analysis Supports SQN Operation & Accident Mitigation & Methods Used to Keep SQN Personnel Aware of Offsite Power Sys Condition Project stage: Other ML20210H8691997-08-0505 August 1997 Provides Suppl Info Re Analysis Performed by TVA to Support Reliability of Offsite Power Sys,Per 970710 Telcon Project stage: Other 1997-01-17
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M4461999-10-20020 October 1999 Forwards Rev 8 to Sequoyah Nuclear Plant Physical Security/ Contingency Plan, IAW 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20217J4151999-10-15015 October 1999 Forwards Request for Addl Info Re Util 990624 Application for Amend of TSs That Would Revise TS for Weighing of Ice Condenser Ice Baskets 05000327/LER-1999-002, Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project1999-10-15015 October 1999 Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project ML20217G1141999-10-0707 October 1999 Responds to from P Salas,Providing Response to NRC Risk Determination Associated with 990630 Flooding Event at Sequoyah Facility.Meeting to Discuss Risk Determination Issues Scheduled for 991021 in Atlanta,Ga ML20217B2981999-10-0606 October 1999 Discusses Closeout of GL 92-01,rev 1,suppl 1, Reactor Vessel Integrity, for Sequoyah Nuclear Plant,Units 1 & 2. NRC Also Hereby Solicits Any Written Comments That TVA May Have on Current Rvid Data by 991101 ML20217B8431999-10-0505 October 1999 Requests NRC Review & Approval of ASME Code Relief Requests That Were Identified in Plant Second 10-yr ISI Interval for Both Units.Encl 3 Provides Util Procedure for Calculation of ASME Code Coverage for Section XI Nondestructive Exams IR 05000327/19990041999-10-0101 October 1999 Ack Receipt of Providing Comments on Insp Repts 50-327/99-04 & 50-328/99-04.NRC Considered Comments for Apparent Violation Involving 10CFR50.59 Issue ML20217C7101999-10-0101 October 1999 Forwards Response to NRC 990910 RAI Re Sequoyah Nuclear Plant,Units 1 & 2 URI 50-327/98-04-02 & 50-328/98-04-02 Re Ice Weight Representative Sample ML20212J5981999-10-0101 October 1999 Forwards SE Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plnat,Unit 1 ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program ML20217A9451999-09-27027 September 1999 Forwards Insp Repts 50-327/99-05 & 50-328/99-05 on 990718- 0828.One Violation Identified & Being Treated as Non-Cited Violation ML20216J9351999-09-27027 September 1999 Responds to NRC Re Violations Noted in Insp Repts 50-327/99-04 & 50-328/99-04.Corrective Actions:Risk Determination Evaluation Was Performed & Licensee Concluded That Event Is in Green Regulatory Response Band ML20212F0751999-09-23023 September 1999 Forwards SER Granting Util 981021 Request for Relief from ASME Code,Section XI Requirements from Certain Inservice Insp at Sequoyah Nuclear Power Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) ML20212F4501999-09-23023 September 1999 Forwards Amends 246 & 237 to Licenses DPR-77 & DPR-79, Respectively & Ser.Amends Approve Request to Revise TSs to Allow Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20212M1911999-09-21021 September 1999 Discusses Exercise of Enforcement Discretion Re Apparent Violation Noted in Insp Repts 50-327/99-04 & 50-328/99-04 Associated with Implementation of Procedural Changes Which Resulted in Three Containment Penetrations Being Left Open ML20211Q0311999-09-10010 September 1999 Requests Written Documentation from TVA to Provide Technical Assistance to Region II Re TS Compliance & Ice Condenser Maint Practices at Plant ML20216F5441999-09-0707 September 1999 Provides Results of Risk Evaluation of 990630,flooding Event at Sequoyah 1 & 2 Reactor Facilities.Event Was Documented in Insp Rept 50-327/99-04 & 50-328/99-04 & Transmitted in Ltr, ML20211N5681999-09-0101 September 1999 Submits Clarification of Two Issues Raised in Insp Repts 50-327/99-04 & 50-328/99-04,dtd 990813,which Was First Insp Rept Issued for Plant Under NRC Power Reactor Oversight Process Pilot Plant Study ML20211G5881999-08-27027 August 1999 Submits Summary of 990820 Management Meeting Re Plant Performance.List of Attendees & Matl Used in Presentation Enclosed ML20211F8891999-08-25025 August 1999 Forwards Sequoyah Nuclear Plant Unit 1 Cycle 9 Refueling Outage, Re Completed SG Activities,Per TSs 4.4.5.5.b & 4.4.5.5.c ML20211A1851999-08-16016 August 1999 Forwards Proprietary TR WCAP-15128 & non-proprietary Rept WCAP-15129 for NRC Review.Repts Are Provided in Advance of TS Change That Is Being Prepared to Support Cycle 10 Rfo. Proprietary TR Withheld,Per 10CFR2.790 ML20210V1471999-08-13013 August 1999 Forwards Insp Repts 50-327/99-04 & 50-328/99-04 on 990601- 0717.One Potentially Safety Significant Issue Identified.On 990630,inadequate Performance of Storm Drain Sys Caused Water from Heavy Rainfall to Backup & Flood Turbine Bldg ML20211A1921999-08-12012 August 1999 Requests Proprietary TR WCAP-15128, Depth-Based SG Tube Repair Criteria for Axial PWSCC at Dented TSP Intersections, Be Withheld from Public Disclosure Per 10CFR2.790 ML20210Q5011999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006 at Sequoyah Nuclear Plant. Sample Registration Ltr Encl ML20210L4291999-08-0202 August 1999 Forwards Sequoyah Nuclear Plant Unit 2 Cycle 9 12-Month SG Insp Rept & SG-99-07-009, Sequoyah Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept. Repts Submitted IAW TS 4.4.5.5.b & TS 4.4.5.5.c ML20210L1611999-07-30030 July 1999 Forwards Request for Relief RV-4 Re ASME Class 1,2 & 3 Prvs, Per First ten-year Inservice Test Time Interval.Review & Approval of RV-4 Is Requested to Support Unit 1 Cycle 10 Refueling Outage,Scheduled to Start 000213 ML20210G5301999-07-28028 July 1999 Forwards Sequoyah Nuclear Plant Unit 2 ISI Summary Rept That Contains Historical Record of Repairs,Replacement & ISI & Augmented Examinations That Were Performed on ASME Code Class 1 & 2 Components from 971104-990511 ML20211B9661999-07-26026 July 1999 Informs That Sequoyah Nuclear Plant Sewage Treatment Plant, NPDES 0026450 Outfall 112,is in Standby Status.Flow Has Been Diverted from Sys Since Jan 1998 ML20210B2521999-07-14014 July 1999 Confirms 990712 Telcon Between J Smith of Licensee Staff & M Shannon of NRC Re semi-annual Mgt Meeting Schedule for 990820 in Atlanta,Ga to Discuss Recent Sequoyah Nuclear Plant Performance ML20210J1091999-07-10010 July 1999 Submits Suggestions & Concerns Re Y2K & Nuclear Power Plants ML20196K0381999-06-30030 June 1999 Provides Written Confirmation of Completed Commitment for Final Implementation of Thermo-Lag 330-1 Fire Barrier Corrective Actions at Snp,Per GL 92-08 ML20209E4071999-06-30030 June 1999 Forwards Insp Repts 50-327/99-03 & 50-328/99-03 on 990328- 0531.Violations Being Treated as Noncited Violations ML20196J8261999-06-28028 June 1999 Forwards Safety Evaluation Authorizing Request for Relief from ASME Boiler & Pressure Vessel Code,Section XI Requirements for Certain Inservice Inspections at Sequoyah Nuclear Plant,Units 1 & 2 ML20196G7881999-06-22022 June 1999 Informs NRC of Changes That Util Incorporated Into TS Bases Sections & Trm.Encl Provides Revised TS Bases Pages & TRM Affected by Listed Revs ML20196G1801999-06-21021 June 1999 Requests Termination of SRO License SOP-20751-1,for Lf Hardin,Effective 990611.Subject Individual Resigned from Position at TVA ML20195G1821999-06-0808 June 1999 Requests NRC Review & Approval of ASME Code Relief for ISI Program.Encl 1 Provides Relief Request 1-ISI-14 That Includes Two Attachments.Encl 2 Provides Copy of Related ASME Code Page ML20195E9521999-06-0707 June 1999 Requests Relief from Specific Requirements of ASME Section Xi,Subsection IWE of 1992 Edition,1992 Addenda.Util Has Determined That Proposed Alternatives Would Provide Acceptable Level of Quality & Safety ML20195E9311999-05-28028 May 1999 Informs of Planned Insp Activities for Licensee to Have Opportunity to Prepare for Insps & Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20195B3631999-05-21021 May 1999 Requests Termination of SRO License for Tj Van Huis,Per 10CFR50.74(a).TJ Van Huis Retired from Util,Effective 990514 ML20207A5721999-05-20020 May 1999 Forwards Correction to Previously Issued Amend 163 to License DPR-79 Re SR 4.1.1.1.1.d Inadvertently Omitted from Pp 3/4 1-1 of Unit 2 TS ML20206Q8791999-05-13013 May 1999 Forwards L36 9990415 802, COLR for Sequoyah Nuclear Plant Unit 2,Cycle 10, IAW Plant TS 6.9.1.14.c 05000327/LER-1999-001, Forwards LER 99-001-00 Re Condition That Resulted in Granting of Enforcement Discretion,Per Failure of Centrifugal Charging Pump.Condition Being Reported IAW 10CFR50.73(a)(2)(i)(B) & (a)(2)(iv)1999-05-11011 May 1999 Forwards LER 99-001-00 Re Condition That Resulted in Granting of Enforcement Discretion,Per Failure of Centrifugal Charging Pump.Condition Being Reported IAW 10CFR50.73(a)(2)(i)(B) & (a)(2)(iv) ML20206M9341999-05-10010 May 1999 Forwards Rept of SG Tube Plugging During Unit 2 Cycle 9 Refueling Outage,As Required by TS 4.4.5.5.a.ISI of Unit 2 SG Tubes Was Completed on 990503 ML20206K6271999-05-0606 May 1999 Requests Termination of SRO License for MR Taggart,License SOP-21336 Due to Resignation on 990430 ML20206J2061999-05-0404 May 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME B&PV Code.Tva Requests Approval to Use Wire Type Penetrameters in Lieu of Plaque Type Penetrameters for Performing Radiographic Insps.Specific Relief Request,Encl ML20209J0391999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept, Radiological Impact Assessment Rept & Rev 41 to ODCM, for Period of Jan-Dec 1998 ML20206C6541999-04-23023 April 1999 Forwards Response to NRC 990127 RAI Re GL 96-05 for Sequoyah Nuclear Plant,Units 1 & 2 ML20206C0841999-04-23023 April 1999 Forwards Insp Repts 50-327/99-02 & 50-328/99-02 on 990214-0327.No Violations Noted ML20206B9591999-04-20020 April 1999 Responds to 990417 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in Unit 1 TS 3.1.2.2,3.1.2.4 & 3.5.2 & Documents 990417 Telephone Conversation When NRC Orally Issued NOED ML20205S5891999-04-17017 April 1999 Documents Request for Discretionary Enforcement for Unit 1 TS LCOs 3.1.2.2,3.1.2.4 & 3.5.2 to Support Completion of Repairs & Testing for 1B-B Centrifugal Charging Pump (CCP) 1999-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217M4461999-10-20020 October 1999 Forwards Rev 8 to Sequoyah Nuclear Plant Physical Security/ Contingency Plan, IAW 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 05000327/LER-1999-002, Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project1999-10-15015 October 1999 Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project ML20217B8431999-10-0505 October 1999 Requests NRC Review & Approval of ASME Code Relief Requests That Were Identified in Plant Second 10-yr ISI Interval for Both Units.Encl 3 Provides Util Procedure for Calculation of ASME Code Coverage for Section XI Nondestructive Exams ML20217C7101999-10-0101 October 1999 Forwards Response to NRC 990910 RAI Re Sequoyah Nuclear Plant,Units 1 & 2 URI 50-327/98-04-02 & 50-328/98-04-02 Re Ice Weight Representative Sample ML20216J9351999-09-27027 September 1999 Responds to NRC Re Violations Noted in Insp Repts 50-327/99-04 & 50-328/99-04.Corrective Actions:Risk Determination Evaluation Was Performed & Licensee Concluded That Event Is in Green Regulatory Response Band ML20211N5681999-09-0101 September 1999 Submits Clarification of Two Issues Raised in Insp Repts 50-327/99-04 & 50-328/99-04,dtd 990813,which Was First Insp Rept Issued for Plant Under NRC Power Reactor Oversight Process Pilot Plant Study ML20211F8891999-08-25025 August 1999 Forwards Sequoyah Nuclear Plant Unit 1 Cycle 9 Refueling Outage, Re Completed SG Activities,Per TSs 4.4.5.5.b & 4.4.5.5.c ML20211A1851999-08-16016 August 1999 Forwards Proprietary TR WCAP-15128 & non-proprietary Rept WCAP-15129 for NRC Review.Repts Are Provided in Advance of TS Change That Is Being Prepared to Support Cycle 10 Rfo. Proprietary TR Withheld,Per 10CFR2.790 ML20211A1921999-08-12012 August 1999 Requests Proprietary TR WCAP-15128, Depth-Based SG Tube Repair Criteria for Axial PWSCC at Dented TSP Intersections, Be Withheld from Public Disclosure Per 10CFR2.790 ML20210L4291999-08-0202 August 1999 Forwards Sequoyah Nuclear Plant Unit 2 Cycle 9 12-Month SG Insp Rept & SG-99-07-009, Sequoyah Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept. Repts Submitted IAW TS 4.4.5.5.b & TS 4.4.5.5.c ML20210L1611999-07-30030 July 1999 Forwards Request for Relief RV-4 Re ASME Class 1,2 & 3 Prvs, Per First ten-year Inservice Test Time Interval.Review & Approval of RV-4 Is Requested to Support Unit 1 Cycle 10 Refueling Outage,Scheduled to Start 000213 ML20210G5301999-07-28028 July 1999 Forwards Sequoyah Nuclear Plant Unit 2 ISI Summary Rept That Contains Historical Record of Repairs,Replacement & ISI & Augmented Examinations That Were Performed on ASME Code Class 1 & 2 Components from 971104-990511 ML20210J1091999-07-10010 July 1999 Submits Suggestions & Concerns Re Y2K & Nuclear Power Plants ML20196K0381999-06-30030 June 1999 Provides Written Confirmation of Completed Commitment for Final Implementation of Thermo-Lag 330-1 Fire Barrier Corrective Actions at Snp,Per GL 92-08 ML20196G7881999-06-22022 June 1999 Informs NRC of Changes That Util Incorporated Into TS Bases Sections & Trm.Encl Provides Revised TS Bases Pages & TRM Affected by Listed Revs ML20196G1801999-06-21021 June 1999 Requests Termination of SRO License SOP-20751-1,for Lf Hardin,Effective 990611.Subject Individual Resigned from Position at TVA ML20195G1821999-06-0808 June 1999 Requests NRC Review & Approval of ASME Code Relief for ISI Program.Encl 1 Provides Relief Request 1-ISI-14 That Includes Two Attachments.Encl 2 Provides Copy of Related ASME Code Page ML20195E9521999-06-0707 June 1999 Requests Relief from Specific Requirements of ASME Section Xi,Subsection IWE of 1992 Edition,1992 Addenda.Util Has Determined That Proposed Alternatives Would Provide Acceptable Level of Quality & Safety ML20195B3631999-05-21021 May 1999 Requests Termination of SRO License for Tj Van Huis,Per 10CFR50.74(a).TJ Van Huis Retired from Util,Effective 990514 ML20206Q8791999-05-13013 May 1999 Forwards L36 9990415 802, COLR for Sequoyah Nuclear Plant Unit 2,Cycle 10, IAW Plant TS 6.9.1.14.c 05000327/LER-1999-001, Forwards LER 99-001-00 Re Condition That Resulted in Granting of Enforcement Discretion,Per Failure of Centrifugal Charging Pump.Condition Being Reported IAW 10CFR50.73(a)(2)(i)(B) & (a)(2)(iv)1999-05-11011 May 1999 Forwards LER 99-001-00 Re Condition That Resulted in Granting of Enforcement Discretion,Per Failure of Centrifugal Charging Pump.Condition Being Reported IAW 10CFR50.73(a)(2)(i)(B) & (a)(2)(iv) ML20206M9341999-05-10010 May 1999 Forwards Rept of SG Tube Plugging During Unit 2 Cycle 9 Refueling Outage,As Required by TS 4.4.5.5.a.ISI of Unit 2 SG Tubes Was Completed on 990503 ML20206K6271999-05-0606 May 1999 Requests Termination of SRO License for MR Taggart,License SOP-21336 Due to Resignation on 990430 ML20206J2061999-05-0404 May 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME B&PV Code.Tva Requests Approval to Use Wire Type Penetrameters in Lieu of Plaque Type Penetrameters for Performing Radiographic Insps.Specific Relief Request,Encl ML20209J0391999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept, Radiological Impact Assessment Rept & Rev 41 to ODCM, for Period of Jan-Dec 1998 ML20206C6541999-04-23023 April 1999 Forwards Response to NRC 990127 RAI Re GL 96-05 for Sequoyah Nuclear Plant,Units 1 & 2 ML20205S5891999-04-17017 April 1999 Documents Request for Discretionary Enforcement for Unit 1 TS LCOs 3.1.2.2,3.1.2.4 & 3.5.2 to Support Completion of Repairs & Testing for 1B-B Centrifugal Charging Pump (CCP) ML20205B1091999-03-19019 March 1999 Submits Response to NRC Questions Concerning Lead Test Assembly Matl History,Per Request ML20204H0161999-03-19019 March 1999 Resubmits Util 990302 Response to Violations Noted in Insp Repts 50-327/98-11 & 50-328/98-11.Corrective Actions:Lessons Learned from Event Have Been Provided to Operating Crews ML20204E8251999-03-0505 March 1999 Forwards Sequoyah Nuclear Plant,Four Yr Simulator Test Rept for Period Ending 990321, in Accordance with Requirements of 10CFR55.45 ML20207E6851999-03-0202 March 1999 Responds to NRC Re Violations Noted in Insp Repts 50-327/98-11 & 50-328/98-11.Corrective Actions:Lessons Learned from Event Have Been Provided to Operating Crews ML20207J1171999-01-29029 January 1999 Forwards Copy of Final Exercise Rept for Full Participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to Sequoyah NPP ML20202A7141999-01-20020 January 1999 Provides Request for Relief for Delaying Repair on Section of ASME Code Class 3 Piping within Essential Raw Cooling Water Sys ML20198S7141998-12-29029 December 1998 Forwards Cycle 10 Voltage-Based Repair Criteria 90-Day Rept, Per GL 95-05.Rept Is Submitted IAW License Condition 2.C.(9)(d) 05000327/LER-1998-004, Forwards LER 98-004-00,providing Details Concerning Inability to Complete Surveillance within Required Time Interval1998-12-21021 December 1998 Forwards LER 98-004-00,providing Details Concerning Inability to Complete Surveillance within Required Time Interval ML20198D5471998-12-14014 December 1998 Requests That License OP-20313-2 for Je Wright,Be Terminated IAW 10CFR50.74(a).Individual Retiring ML20197J5541998-12-10010 December 1998 Forwards Unit 1 Cycle 9 90-Day ISI Summary Rept IAW IWA-6220 & IWA-6230 of ASME Code,Section Xi.Request for Relief Will Be Submitted to NRC Timeframe to Support Second 10-year Insp Interval,Per 10CFR50.55a 05000327/LER-1998-003, Forwards LER 98-003-00 Re Automatic Reactor Trip with FW Isolation & Auxiliary FW Start as Result of Failure of Vital Inverter & Second Inverter Failure.Event Is Being Reported IAW 10CFR50.73(a)(2)(iv)1998-12-0909 December 1998 Forwards LER 98-003-00 Re Automatic Reactor Trip with FW Isolation & Auxiliary FW Start as Result of Failure of Vital Inverter & Second Inverter Failure.Event Is Being Reported IAW 10CFR50.73(a)(2)(iv) ML20196F9841998-11-25025 November 1998 Provides Changes to Calculated Peak Fuel Cladding Temp, Resulting from Recent Changes to Plant ECCS Evaluation Model ML20195H7891998-11-17017 November 1998 Requests NRC Review & Approval of Five ASME Code Relief Requests Identified in Snp Second ten-year ISI Interval for Units 1 & 2 ML20195E4991998-11-12012 November 1998 Forwards Rev 7 to Physical Security/Contingency Plan.Rev Adds Requirement That Security Personnel Will Assess Search Equipment Alarms & Add Definition of Major Maint.Rev Withheld (Ref 10CFR2.790(d)(1)) 05000328/LER-1998-002, Forwards LER 98-002-00 Re Automatic Turbine & Reactor Trip, Resulting from Failure of Sudden Pressure Relay on 'B' Phase Main Transformer1998-11-10010 November 1998 Forwards LER 98-002-00 Re Automatic Turbine & Reactor Trip, Resulting from Failure of Sudden Pressure Relay on 'B' Phase Main Transformer ML20195G5701998-11-10010 November 1998 Documents Util Basis for 981110 Telcon Request for Discretionary Enforcement for Plant TS 3.8.2.1,Action B,For 120-VAC Vital Instrument Power Board 1-IV.Licensee Determined That Inverter Failed Due to Component Failure ML20155J4031998-11-0505 November 1998 Provides Clarification of Topical Rept Associated with Insertion of Limited Number of Lead Test Assemblies Beginning with Unit 2 Operating Cycle 10 Core ML20154R9581998-10-21021 October 1998 Requests Approval of Encl Request for Relief ISI-3 from ASME Code Requirements Re Integrally Welded Attachments of Supports & Restraints for AFW Piping ML20155B1481998-10-21021 October 1998 Informs That as Result of Discussion of Issues Re Recent Events in Ice Condenser Industry,Ice Condenser Mini-Group (Icmg),Decided to Focus Efforts on Review & Potential Rev of Ice condenser-related TS in Order to Clarify Issues ML20154K1581998-10-13013 October 1998 Forwards Rept Re SG Tube Plugging Which Occurred During Unit 1 Cycle 9 Refueling Outage,Per TS 4.4.5.5.a.ISI of Unit 1 SG Was Completed on 980930 ML20154H6191998-10-0808 October 1998 Forwards Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 COLR, IAW TS 6.9.1.14.c 05000328/LER-1998-001, Forwards LER 98-001-00 Providing Details Re Automatic Turbine & Reactor Trip Due to Failure of Sudden Pressure Relay on 'B' Phase Main Transformer1998-09-28028 September 1998 Forwards LER 98-001-00 Providing Details Re Automatic Turbine & Reactor Trip Due to Failure of Sudden Pressure Relay on 'B' Phase Main Transformer ML20151W4901998-09-0303 September 1998 Responds to NRC Re Violations Noted in Insp Repts 50-327/98-07 & 50-328/98-07.Corrective Actions:Revised Per SQ971279PER to Address Hardware Issues of Hysteresis, Pressure Shift & Abnormal Popping Noise 1999-09-27
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IUA Tennessee Valley Authonty Pos! OMce Bon 2000 Sod @Da>sy. Tennessee 37379 July 17,1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk l Washington, D.C. 20555 Gentlemen:
In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SON)- RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION - RELIABILITY OF OFFSITE POWER STUDY (TIA 94-021)(TAC i NOS. M93319 AND M93320) 1
Reference:
NRC Letter to TVA dated March 27,1996," Request for Additional Information - Reliability of Offsite Power Study (TIA 94-021)- Sequoyah j Nuclear Plant Units 1 and 2 (TAC Nos. M93319 and M93320)"
The purpose of this letter is to provide NRC with the response to the request for additional information in the referenced letter. By the reference, NRC requested TVA to provide analysis (or other justification) to demonstrate that the immediate access offsite circuits from the transmission network to the Sequoyah facility will remain connected to safety system loads as their source of power for all anticipated transmission network contingencies, including the worst-case contingency (intertie transformer out of service with a postulated loss-of-coolant accident [LOCA) in Unit 2). The enclosure provides TVA's response and includes justifications that voltage at the safety buses will not go below 5520 Volts for greater than the minimum technical specification (TS) limit of one second and this voltage will not go below 6456 Volts without recovery to a voltage above 6595.5 Volts within the (
minimum TS limit of 7.5 seconds. These justifications show that the SON under I voltage protection design will not trip the offsite circuits and sequence the safety loads onto the diesel generators due to transient voltages on the transmission network gp j immediately after trip of Unit 2 due to a LOCA condition. <-
l The calculations referenced in the enclosure are available for NRC review at the SON site.
l 9607230142 960717 PDR ADOCK 05000327 P PDR L
I 4-l '.
l l.
L U.S. Nuclear Regulatory Commission
- Pa0e 2 July 17,1996 Please direct questions concerning this issue to Keith Weller at (423) 843-7527.
Sincerely, 4M.RW '
R. H. Shell Manager SON Site Licensing Enclosure l
cc (Enclosure): l Mr. R. W. Hernan, Project Manager Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike l
Rockville, Maryland 20852-2739-NRC Resident inspector
, Sequoyah Nuclear Plant -
! 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 !
Regional Administrator l U.S. Nuclear Regulatory Commission Region ll' 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 i
l l
l l
l l
1 ENCLOSURE i
RELIABILITY OF OFFSITE POWER TO SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2.
I Calculation SON-EEB-MS-T106-0002 evaluates the minimum voltage levels at the shutdown and unit boards utilizing the 153 kV from the offsite power supply. That is, with the intertie transformer out of service, the limiting case is for the 161-kV switchyard going from 166 kV, prior to the event, to 153 kV, after the event I (SON EEB-MS-Tl06-0002,Section 4.15). The load tap changers for the common !
station service transformers (CSSTs) will be in a boosting position since the CSST l secondary voltage will be dropping below 7,004 volts. Load tap changers are set to maintain 7052 Volts f_48 Volts at the start buses ahead of the unit boards which I supply power to the shutdown boards (SON-EEB-MS-T106-0002,Section 6.1).
Prior to the loss-of-coolant accident (LOCA) event for Unit 2 on the 161-kV system, the steady state voltages for the unit and shutdown boards will be above 100% of
);
6,900 rated Volts (SON-EEB-MS-T106-0002, running voltage summary). At T= 0 sec., the board voltages will drop to as low as 5861.6 Volts (SON-EEB-MS-Tl06-0002, l Motor Start Voltage Summary, Source 2, Condition 4; S1 PHASE B at T= 0 sec.). This voltage level is above 5,520 Volts, the 80% loss-of-voltage (LOV) TS trip value. Six seconds later, the board voltages will rise above 96%, lowest value 6641.3 Volts (SON-EEB-MS-Tl06-0002, Motor Start Voltage Summary, Source 2, Condition 4; St PHASE B at T= 6 sec.). The voltage rise value, 6641.3 Volts, is above 6595.5 Volts, the TS maximum voltage reset value.
This value,6641.3 Volts,is above the 6.9 kV shutdown board degraded voltage set point,6456 Volts (or 93.5% of 6900 Volt at timer set point = 9.5 seconds). Also, it l Is above the minimum voltage recovery at six seconds following block start of accident loads, 6599 Volts (SON-EEB-MS-Tl06-0008, Degraded Voltage Protection !
Calculation).
I l The Transmission Group Study, SON-GRID-STUDY-004, has provided verification for the adequacy of the offsite power supply. These studies include the new 161-kV capacitors at SON. The load flow studies show that the voltage does not drop below the 153-kV required voltage post-event (steady state voltage one-second post-vent).
For a LOCA in Unit 2, and a simultaneous fault in the intertie bank, the 161-kV voltage will drop to 155.7-kV.
Transient stability studies were also done in SON-GRID-STUDY-004 to examine l voltage recovery times. Two types of studies were performed. The first type was a l
LOCA plus another transmission contingency. These were performed to ensure safe shutdown of the units following an accident. The second type was two transmission i contingencies. These were performed to determine whether transmission events
! could accidentally trip the units. In both studies, voltage recovery times were compared to the following relay settings. The reactor coolant pump (RCP) voltage ;
must recover to 5076 Volts within 38.5 cycles. The shutdown board LOV relays must recover to 5686 Volts within 75 cycles.
l l
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l
4 For a LOCA and a simultaneous fault in the intertie bank such that the bank is tripped, ;
the 161-kV voltage recovered to the 153-kV levelin 6.25 cycles which is well within any of the relay settings.
For a phase to phase to ground fault with a stuck breaker on the 161-kV system the voltage recovers to the RCP reset level in 34.6 cycles and to the LOV reset level in 35.6 cycles. This does not violate any of the relay settings and would therefore not result in an accidental trip of a generator unit.
SON-GRID-STUDY-006is a further Transmission Group Study in evaluating the adequacy of the SON offsite power supply. The approach is to provide two offsite sources that maintain the SON 161-kV bus voltage during normal system conditions, that is to exceed 153 kV during a simulated LOCA of one unit and a simultaneous transmission contingency.
SON-GRID-STUDY-006 concluded that the SON offsite power supply is adequate with two immediate sources, whenever the two 84 MVAR capacitors connected to the SON 161-kV bus are available. Two immediate sources are possible only if specific system indicators are met. The indicators are SON Unit 2 reactive output. SON 161-kV bus voltage, and the SON 500/161-kVintertie transformer bank reactive flow.
The SON capacitors must be in automatic control mode continuously except when the dispatchers deem it necessary to manually switch the capacitors in order to maintain these system indicators. Furthermore, another load flow study, SON-GRID-STUDY-008, augments SON-GRID-STUDY-006 and provides voltage schedules and operation instructions. This study includes a coincident extreme load forecast for the net system load of 28,797 MW. This study also takes into account the outage of 161-kV switchyard breaker 974 which will be out until the summer of 1997.
Conclusion:
Transmission system studies have been performed, which demonstrate that the 161-kV bus will maintain a minimum voltage of 153 kV, both steady state and during transients. SON-EEB-MS-Tl06-002 demonstrates that the 153-kV bus voltage is adequate to support the required safety features. As documented and illustrated in this response, the offsite power under transient conditions will not cause nuisance tripping / alarms as a result of undervoltage at the 6.9-kV unit boards or 6.9-kV shutdown boards.
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1 500kv switchyard (offsite supply) l ;
wm w m 500-161kv intertie l
161kv switchyard (offsite' supply) ;
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wmum CSST A !
um- um 161-6.9kv l x-winding j l
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'6.9kv Start bus IA -l l
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- 6.9kV Unit BD 1C l) l)(EMFdecay+earlytimefor undervoltage & timer relays i
I 38.5 cycles)=
I 27 62 UV Relay & Timer .
OO- l l O RCP !
l 6.9kv Shutdown Bd 1B-B 27D DS SI Degraded voltage & timer O-O n- Re1ay.. na Safety 93.5% 9.5s Injection Contact 80% 1.25s
, -O-O ;
27T LV Loss of Voltage & Timer Rlys TYPICAL SINGLE LINE SUPPLY TO 6.9KV UNIT & SHDN BOARDS
- - - ,,.-4 --
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OFFSITE VOLTAGE RECOVERY CURVE (IN TERNS OF 6900V SYSTEN):
PHASE-PHASE-GROUND FAULT WITH STUCK BKR SITE VOLTAGE RECOVERY CURVE: LOCA + INTERTIE OUT Unit a G.n.cator will b. g.n.roting T-30 sec
/
T-0 T-1 T2 T-3 T-4 T-5 T-6 T-7.5 (166KV) 7114V - -
M1-------------1-----l 7004V - - +- -p - - - - - - - - -t - - - - l l l Y l I
'IC l'a9 6.9KV Shutdown Bd (160KV1 6857V ry i
i Recov.ry low.st volu.l l gg4}y ,_ []f,f elt . Vo l t og. Recovey _ A
_ l fil n Voltage following i I I A' block stortI 6599V I I I I 6595.5V t - - - - - - - - - - - - -t - - - p (153KV) 6557V - - Li 10.g r d.d v t t /
og.I TSpec mox l l y I reset volu. l Sit. Voltog. g Recov.ry 6456V - TT--- - - - - ----
t---
/
7 I I l0. eod.d Vol1o9.l 6.9KV Shutdown Bd 9 .5% of 6900V
/ Iowest vatu. l dropout with SIl 5861.6V -- on =orty on TT (TSpec LOV I 7.5 e.c < Tsp.c l timer trip e.1 1l j* _ Tal.25 see ti..r Lood eh.a e.tting) l point . g.s ,,c 3l 80% LOV r...t volu.
5686V l l p- 'l 34-(Dropout at 5520V os
.orly as T=1 e.c) l (73.6% of 6900V) 5076V -a, 4*~ RCP UV res.1 rDeopout valueos at 5022v .or t y os 38.5 cyi LOV recov.ry in 35.6 cy Phos.-Phoe.-Ground foult RCP voltog. recovery i .n 34.6 cy ,
[85KV) 3644V - -
VOLTAGE RECOVERY D I A G R A l1 l
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'I
- OFFSITE VOLTAGE RECOVERY CURVE IIN TERNS OF 6900V SYSTEMn LOCA + 500/161KV INTERTIE FAULT SITE VOLTAGE RECOVERY CURVE: LOCA + INTERTIE DUT Uni 1 2 Generator wiiI b. 9.n roting T 30 see
/
T-0 T-1 T-2 T3 T-4 T-5 T-6 T-7.5 (166KV) 7114V -
E l- - - - - - - - - - - - - - L - - - _ _ l 7004V , - - t- + - - -t - - - - -l I I
- I I I LTC Boosting 6.9KV Shutdown Bd l I I a.cov.cy to...t voio.1 1 6641V - -.L_L _ _ _ _ _ _ _ _ _ _ _ _'_^ fl i n Voltog. rol l
l l Voltog. recovery at 6.25 cy l / b lock . tor t l low i ng 6599V g l ;
6595.5V -
t---------- -
-t - - - - p I155.7KV) 6673V r :
(l53KV1 6557V I Iy\0 rr.it. Voitog.
tsp., ". ' /** I I I R cov.ry l r...t valu.
y\
g g Sit. Voltog. g Recovery l 6456V - TT--- i t-l l 10.groded VoItog.l
/
6.9KV Shutdown Bd 93.5% or 6900V
/ tow..t votu. Ideopout with 51l 5861.6V a' =ar l y aa TT T=1.25 .e (TSpee LOV 1 7. t ... ITSp.c 1 t i .r trip ..t ll l4 Load sh.d 16..r ..tting) lpo i n t = 9.5 ..c Il 80X LOV r...t volu.
5686V -- - b 14 10r opout at 5520V l l
- o. .orty o. T=1 ..ol l
RCP UV re..t volu. (73.6% or 6900V) i 5076V - -4 *~ l Dr op ou t ,t 5022V a. .orty o. 38.5 eyl l (109KV) 4671V - ---
VOLTAGE RECOVERY DIAGRAM