|
|---|
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
[Table view] |
Text
e O
nn Tennessee Vaney Authonty Post Othce Box 2000 Soddy Daisy. Tennessee 37379 October 13, 1998 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter ) Docket No. 50-327 Tennessee Valley Authority )
SEQUOYAH NUCLEAR PLANT (SQN) - UNIT 1 STEAM GENERATOR (SG)
TUBE PLUGGING REPORT AND NOTIFICATION OF UNIT 1 SG TUBE INSPECTIONS - UNIT,1 CYCLE 91 REFUELING OUTAGE
,c : ... . . .. , _ .
As required by'SQN Technical Specification (TS) 4.4.5.5.a, this submittal provides a report of SG tube plugging during the Unit 1 Cycle 9 refueling outage. The in-service inspection (ISI) of the Unit 1 SG tubes was completed on September 30, 1998. In accordance with SON TS 4.4.5.5.b, TVA will submit a special report of the results of this inspection on or before September 30, 1999.
Pursuant to the reporting requirements of TS 4.4.5.5.c, NRC was notified of the SG tube inspections that fell into Category C-3. Notification of these results was made during a telephone conference call on September 29, 1998. In accordance with SQN TS 3/4.4.5, SGs 3 and 4 U-Bend inspections were classified as Category C-3. The initial Row 1 and 2 U-Bend Plus-Point examination sang'_es were 146 tubes in SG 3 and 155 tubes in SG 4. There were two tubes in SG 3 and three tubes in SG 4 that were determined to have primary water stress corrosion cracking (PWSCC). These tubes are located in Row 1. Since 100 percent of the Row 1 and 2 tubes were examined, no expansion was necessary.
TS 4.4.5.5.c also requires a written follow-up report. TVA plans to provide this information in conjunction with SQN's 90-day alternate plugging report.
"" k 9810160134 981013 i PDR P
ADOCK 05000327-PDR hOcp -.g Q p i
. . , . . - . - - - . . . - . . - .. ._ _ _ . - .-- . ..- .. .. ~ .. . .
e U.S.. Nuclear Regulatory Commi~ssion
.Page ,2 -
October 13, 1998 l In accordance-with TS 4.4.5.5.d, notification was made to the L
estaff during two conference calls on1 September 29 and' October 2, 1998. The September conference call provided notification regarding four SG tubes having indications attributable to PWSCC. The October conference call provided notification of a tube having both a circumferencial and an axial indication in the same tube support plate. This indication was identified initially by bobbin examination as 1 an indication that would require a retest using a rotating l
- coil. The Plus-Point coil identified a circumferential.and l axial'outside diameter stress corrosion cracking at the first l
- hot support plate. This tube was removed from service by !
l - plugging. I I
Enclosed is a summary of the tubes plugged during the Unit 1 Cycle 9. refueling outage. -]
i Please direct questions concerning this i ssue to me at' (423) 843-7170 or~J. D. Smith at (423) 843-6672.
Sincerely, Pedro Salas Site Licensing and Industry Affairs Manager cc (Enclosure):
L Mr. R. W. Hernan, Project Manager l Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant L 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 l -Regional Administrator U.S. Nuclear Regulatory Commission Region II l
Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303-3415
aH A E .A ~- 8 ~n % b 4mi M
ENCLOSURE SEQUOYAH NUCLEAR PLANT UNIT 1 CYCLE 9 REFUELING OUTAGE STEAM GENERATOR TUBE' PLUGGING REPORT l
1 1
j
1 1
1 Steam Generator 15 Day Plugging Report Sequoyah Unit 1 Cycle 9 SG ROW COL INDICATION LOCATION RESOLUTION 1 1 39 SAI H07+10.57 PLUG 1 2 52 SAI HTS .29 PLUG 1 3 59 SAI H01+.51 PLUG 1 4 54 SAI HTS-2.01 PLUG 1 7 47 SCI H01+.00 PLUG 1 9 2 SCI H01+.01 PLUG / STABILIZE 1 17 55 SAI H01+.58 PLUG
- 1 23 88 SAI H01+.00 PLUG 1 26 41 SCI HTS .04 PLUG 1 35 77 SCI HTS +.00 PLUG / STABILIZE Total Number of Tubes Plugged This Generator =10 2 2 92 PTE HTS +.00 PLUG PREVENTIVELY 2 4 15 PI H02 .06 'ULL/ PLUG 2 4 36 SAI HTS +.15 PLUG 2 8 32 41 H01 .17 PLUG 2 10 25 SCI HTS .19 PLUG 2 10 34 36 H01+.06 PLUG 2 11 25 SCI HTS .17 PLUG 2 13 17 SCI HTS .12 PLUG 2 13 18 SCI HTS .14 PLUG 2 14 33 56 H02 .12 PLUG 2 15 29 SCI HTS .10 PLUG 2 16 33 MCI H02+.12 PLUG / STABILIZE 2 16 53 SCI HTS .07 PLUG 2 16 78 SAI HTS-2.74 PLUG 2 17 30 SCI HTS .11 PLUG 2 18 30 59 H01 .17 PLUG 2 19 24 SCI HTS .08 PLUG SAI = Single Axial Indication l SCI = Single Circumferential Indication ;
MCI = Multiple Circumferential Indication BLG = Bulge l PTE = Partial Tubesheet Expansion PI = Axial ODSCC where APC applies i l
. . - . . . .- - ~ .
l j
Steam Generator 15 Day Plugging Report Sequoyah Unit 1 Cycle 9 l SG' ROW COL INDICATION LOCATION RESOLUTION 2 22 34 SCI HTS +.04' ' PLUG / STABILIZE 2 23 33 SCI HTS .03 PLUG 2 25 65 SCI HTS .08 PLUG 2 26 27 SCI HTS .08 PLUG 2 26 50 SCI HTS .06 PLUG 2 29 56 SCI HTS .13 PLUG l Total Number of Tubes Plugged This Generator =23 3 1 89 SAI H07+3.60 PLUG 3 1 90 SAI H07+10.45 PLUG 3 3 53 42 H01 .12 PLUG 3 : 58 52 H01 .04 PLUG l 3 4 60 SCI H01+.02 PLUG 3 5 62 30 H01+.00 PLUG 3 6 45 44 H03 .09 PLUG 3 6 54 SCI H04 .21 PLUG 3 6 64 SAI HTS .29 PLUG 3 6 74 55 H01 .30 PLUG 3 7 36 46 H05 .08 PLUG 3 7 54 SCI H01+ 11 PLUG i 3 7 76 40 H02 .24 PLUG 3 7 83 40 H01+.37 PLUG 3 8 3 49 H03 .05 PLOG 3 9 67 43 H02+.05 PLUG 3 9 83 18 H01 .07 PLUG 3 9 86 SAI H01+.01 PLUG 3 10 36 46 H01 .06 PLUG 3 10 41 40 H01 .14 PLUG 3 10 54 SCI HTS +.06 PLUG 3 10 85 80 H01 .20 PLUG '
l i
l l i I
i !
I i
l
l :
, , j Steam Generator 15 Day Plugging Report !
! Sequoyah Unit 1 Cycle 9 l
SG ROW COL INDICATION LOCATION RESOLUTION 3 11 19 SCI HTS .07 PLUG 3 11 74 46 H01 51 PLUG l 3 12 48 SAI HTS .19 PLUG I 3 12 71 SAI H01 .06 PLUG 3 12 81 SAI H01+.67 PLUG 3 14 57 49 H01 .06 PLUG l 3 14 84 41 H01 .27 PLUG l 3 15 62 SCI H01+.17 PLUG ;
3 16 43 SCI HTS .12 PLUG 3 16 69 39 H01+.46 PLUG 3 18 74 51 H01+.31 PLUG 3 19 68 SCI H01+.03 PLUG 3 21 46 SC1 H01+.15 PLUG 3 21 74 SCI M01+.00 PLUG 3 23 76 57 HG2 .18 PLUG 3 24 80 40 H01 .19 PLUG 3 24 81 SCI H02 .12 PLUG / STABILIZE 3 24 85 54 H01 .03 PLUG 3 25 62 44 H01+.41 PLUG 3 25 76 SAI H01+.06 PLUG 3 26 75 SCI H01 .15 PLUG 3 28 80 SCI H01+.01 PLUG / STABILIZE 3 29 80 44 H01 .25 PLUG l 3 32 70 SCI H01+.17 PLUG 3 33 79 40 H01 .01 PLUG 3 34 52 41 H01+.12 PLUG 3 34 72 SCI H02 .10 PLUG / STABILIZE ,
3 34 76 BLG HTS +.00 PLUG / STABILIZE j 3 35 41 42 AV3+.03 PLUG ;
3 42 56 BLG HTS +3.55 PLUG / STABILIZE I 3 42 60 44 H03 .11 PLUG 3 43 38 45 H01 .18 PLUG 1 3 45 52 46 H02 .07 PLUG i i
Total Number of Tubes Plugged This Generator =55 l
u
Steam Generator 15 Day Plugging Report Sequoyah Unit 1 Cycle 9 SG ROW COL INDICATION LOCATION RESOLUTION 4 1 4 SAI HTS .56 PLUG 4 1 27 SCI H03+.30 PLUG 4 1 77 SCI H07+3.68 PLUG 4 1 80 SAI H07+2.93 ' PLUG 4 1 81 SAI H07+4.07 PLUG 4 2 11 SCI H01 .17 PLUG 4 2 56 43 H01 .25 PLUG 4 3 12 SCI H01+.14 PLUG 4 3 16 SCI H01 .15 PLUG 4 3 75 49 H02 .10 PLUG 4 4 50 SCI H01+.30 PLUG 4 5 33 SCI H01 .24 PLUG 4 6- 15 SCI H03 .07 PLUG 4 6 18 SCI H03 .25 PLUG-4 7 10 SCI H01 .19 PLUG 4 7 75 52 H01+.06 PLUG 4 8 46 SAI HTS .34 PLUG 4 9 38 SCI H01+.21 PLUG 4 10 4 40 H01+.03 PLUG 4 11 35 45 H04+.22 PLUG 4 11 77 52 H03 .27 PLUG 4 12 29 SCI HTS .09 PLUG 4 13 15 SAI HTS 35 PLUG 4 13 37 SCI HTS .11 PLUG 4 13 46 SCI HTS .15 PLUG 4 13 61 97 H03 .40 PLUG 4 15 59 38 H02 .59 PLUG
. 1 i
S$eam Generator 15 Day Plugging Report Sequoyah Unit 1 Cycle 9 SG ROW COL INDICATION LOCATION RESOLUTION 4 17 11 38 H01+.39 PLUG 4 17 53 40 H01 .14 PLUG 4 18 33 SCI HTS .69 PLUG 4 20 44 SCI H01+.00 PLUG 4 21 57 35 H01+.40 PLUG 4 23 43 43 H01+.39 PLUG 4 25 22 MCI H01 .03 PLUG 4 26 12 SAI H01+.00 PLUG 4 26 63 46 H02 .29 PLUG 4 28 24 SCI H01+.00 PLUG 4 28 52 52 H01 .09 PLUG 4 31 18 57 H01 .33 PLUG 1 4 38 38 SCI H01 .11 PLUG / STABILIZE !
4 39 36 SCI H01- .11 PLUG 4 41 27 SAI HTS .10 PLUG Total Number of Tubes Plugged This Generator =42 i
i i
