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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
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K6661990-09-17017 September 1990 Forwards Evaluation That Provides Details of Plug Cracks & Justification for Continued Operation Until 1993 ML20059H4031990-09-10010 September 1990 Discusses Plant Design Baseline & Verification Program Deficiency D.4.3-3 Noted in Insp Repts 50-327/86-27 & 50-328/86-27.Evaluation Concluded That pre-restart Walkdown Data,Loops 1 & 2 Yielded Adequate Design Input ML20059E1851990-08-31031 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-327/90-22 & 50-328/90-22.Corrective Actions:Extensive Mgt Focus Being Applied to Improve Overtime Use Controls ML20059E2881990-08-31031 August 1990 Forwards Addl Info Re Alternate Testing of Reactor Vessel Head & Internals Lifting Rigs,Per NUREG-0612.Based on Listed Hardships,Util Did Not Choose 150% Load Test Option ML20059H1831990-08-31031 August 1990 Forwards Nonproprietary PFE-F26NP & Proprietary PFE-F26, Sequoyah Nuclear Plan Unit 1,Cycle 5 Restart Physics Test Summary, Re Testing Following Vantage 5H Fuel Assembly installation.PFE-F26 Withheld (Ref 10CFR2.790(b)(4)) ML18033B5031990-08-31031 August 1990 Forwards Financial Info Required to Assure Retrospective Premiums,Per 10CFR140 & 771209 Ltr ML20028G8341990-08-28028 August 1990 Forwards Calculation SCG1S361, Foundation Investigation of ERCW Pumping Station Foundation Cells. ML20063Q2471990-08-20020 August 1990 Submits Implementation Schedule for Cable Tray Support Program.Util Proposes Deferral of Portion of Remaining Activities Until After Current Unit 2 Cycle 4 Refueling Outage,Per 900817 Meeting.Tva Presentation Matl Encl ML20056B5181990-08-20020 August 1990 Responds to NRC Re Order Imposing Civil Monetary Penalty & Violations Noted in Insp Repts 50-327/90-01 & 50-328/90-01.Corrective Actions:Organizational Capabilities Reviewed.Payment of Civil Penalty Wired to NRC ML20063Q2461990-08-17017 August 1990 Forwards Cable Test Program Resolution Plan to Resolve Issues Re Pullbys,Jamming & Vertical Supported Cable & TVA- Identified Cable Damage.Tva Commits to Take Actions Prior to Startup to Verify Integrity of safety-related Cables ML20059A5121990-08-15015 August 1990 Provides Clarification of Implementation of Replacement Items Project at Plant for Previously Procured Warehouse Inventory.Util Committed to 100% Dedication of Commercial Grade,Qa,Level Ii,Previous Procurement Warehouse Spare ML20058M2321990-08-0707 August 1990 Forwards Rept of 900709 Fishkill,Per Requirements in App B, Environ Tech Spec,Subsections 4.1.1 & 5.4.2.Sudden Water Temp Increase Killed Approximately 150 Fish in Plant Diffuser Pond ML20058N2361990-08-0707 August 1990 Confirms That Requalification Program Evaluation Ref Matl Delivered to Rd Mcwhorter on 900801.Ref Matl Needed to Support NRC Preparation for Administering Licensed Operator Requalification Exams in Sept 1990 ML20058M4471990-07-27027 July 1990 Responds to Unresolved Items Which Remain Open from Insp Repts 50-327/90-18 & 50-328/90-18.TVA in Agreement W/Nrc on Scope of Work Required to Address Concerns W/Exception of Design Basis Accident & Zero Period Accelaration Effects ML20058M0111990-07-27027 July 1990 Forwards Addl Info Re Plant Condition Adverse to Quality Rept Concerning Operability Determination.Probability of Cable Damage During Installation Low.No Programmatic Cable Installation Problems Exist ML20055J3531990-07-27027 July 1990 Forwards Revised Commitment to Resolve EOP Step Deviation Document Review Comments ML20055J0771990-07-26026 July 1990 Requests Termination of Senior Reactor Operator License SOP-20830 for Jh Sullivan Due to Resignation from Util ML20055G6611990-07-17017 July 1990 Forwards Justification for Continued Operation for safety- Related Cables Installed at Plant,Per 900717 Telcon.No Operability Concern Exists at Plant & No Programmatic Problems Have Been Identified.Summary of Commitments Encl ML20058L7001990-07-16016 July 1990 Forwards Response to SALP Repts 50-327/90-09 & 50-328/90-09 for 890204 - 900305,including Corrective Actions & Improvements Being Implemented ML20055F6151990-07-13013 July 1990 Provides Addl Bases for Util 900320 Proposal to Discontinue Review to Identify Maint Direct Charge molded-case Circuit Breakers Procured Between Aug 1983 & Dec 1984,per NRC Bulletin 88-010.No Significant Assurance Would Be Expected ML20044B2211990-07-12012 July 1990 Forwards Addl Info Clarifying Certain Conclusions & Recommendation in SER Re First 10-yr Interval Inservice Insp Program ML20055D2531990-07-0202 July 1990 Provides Status of Q-list Development at Plant & Revises Completion Date for Effort.Implementation of Q-list Would Cause Unnecessary & Costly Delays in Replanning Maint,Mod, outage-related Activities & Associated Procedure Revs ML20043H9061990-06-21021 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementaion of Generic Safety Issues Resolved W/Imposition or Requirements or Corrective Actions. No Commitments Contained in Submittal ML20043H2281990-06-18018 June 1990 Informs of Issue Recently Identified During Startup of Facility from Cycle 4 Refueling Outage & How Issue Addressed to Support Continued Escalation to 100% Power,Per 900613 & 14 Telcons ML20043G4901990-06-14014 June 1990 Forwards Tabs for Apps a & B to Be Inserted Into Util Consolidated Nuclear Power Radiological Emergency Plan ML20043F9261990-06-13013 June 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Model S3502 Swing Check Valves or Valves of Similar Design. ML20043F9301990-06-13013 June 1990 Responds to NRC 900516 Ltr Re Violations Noted in Insp Repts 50-327/90-17 & 50-328/90-17.Corrective Action:Test Director & Supervisor Involved Given Appropriate Level of Disciplinary Action ML20043H0361990-06-11011 June 1990 Forwards Supplemental Info Re Unresolved Item 88-12-04 Addressing Concern W/Double Differentiation Technique Used to Generate Containment Design Basis Accident Spectra,Per 900412 Request ML20043D9921990-06-0505 June 1990 Responds to NRC 900507 Ltr Re Violations Noted in Insp Repts 50-327/90-14 & 50-328/90-14.Corrective Actions:Util Reviewed Issue & Determined That Trains a & B Demonstrated Operable in Jan & Apr,Respectively of 1989 ML20043C2821990-05-29029 May 1990 Requests Relief from ASME Section XI Re Hydrostatic Pressure Test Requirements Involving RCS & Small Section of Connected ECCS Piping for Plant.Replacement & Testing of Check Valve 1-VLV-63-551 Presently Scheduled for Completion on 900530 ML20043C0581990-05-29029 May 1990 Forwards Response to NRC 900426 Ltr Re Violations Noted in Insp Repts 50-327/90-15 & 50-328/90-15.Response Withheld (Ref 10CFR73.21) ML20043B3051990-05-22022 May 1990 Forwards Detailed Scenario for 900711 Radiological Emergency Plan Exercise.W/O Encl ML20043B1201990-05-18018 May 1990 Forwards, Diesel Generator Voltage Response Improvement Rept. Combined Effect of Resetting Exciter Current Transformers to Achieve flat-compounding & Installing Electronic Load Sequence Timers Produced Acceptable Voltage ML20043A6101990-05-15015 May 1990 Forwards Rev 16 to Security Personnel Training & Qualification Plan.Rev Withheld (Ref 10CFR2.790) ML20043A2391990-05-15015 May 1990 Forwards Revised Tech Spec Pages to Support Tech Spec Change 89-27 Re Steam Generator Water Level Adverse Trip Setpoints for Reactor Trip Sys Instrumentation & Esfas. Encl Reflects Ref Leg Heatup Environ Allowance ML20043A0581990-05-11011 May 1990 Forwards Cycle 5 Redesign Peaking Factor Limit Rept for Facility.Unit Redesigned During Refueling Outage Due to Removal & Replacement of Several Fuel Assemblies Found to Contain Leaking Fuel Rods ML20043A0571990-05-10010 May 1990 Forwards List of Commitments to Support NRC Review of Eagle 21 Reactor Protection Sys Function Upgrade,Per 900510 Telcon ML20042G9771990-05-0909 May 1990 Responds to NRC 900412 Ltr Re Violations Noted in Insp Repts 50-327/90-01 & 50-328/90-01 & Proposed Imposition of Civil Penalty.Corrective Actions:Rhr Pump 1B-B Handswitch in pull- to-lock Position to Ensure One Train of ECCS Operable ML20042G4651990-05-0909 May 1990 Provides Addl Info Re Plant Steam Generator Low Water Level Trip Time Delay & Function of P-8 Reactor Trip Interlock,Per 900430 Telcon.Trip Time Delay Does Not Utilize P-8 Interlock in Any Manner ML20042G4541990-05-0909 May 1990 Provides Notification of Steam Generator Tube Plugging During Unit 1 Cycle 4 Refueling Outage,Per Tech Specs 4.4.5.5.a.Rept of Results of Inservice Insp to Be Submitted by 910427.Summary of Tubes Plugged in Unit 1 Encl ML20042G0441990-05-0808 May 1990 Forwards Nonproprietary WCAP-11896 & WCAP-8587,Suppl 1 & Proprietary WCAP-8687,Suppls 2-E69A & 2-E69B & WCAP-11733 Re Westinghouse Eagle 21 Process Protection Sys Components Equipment Qualification Test Rept.Proprietary Rept Withheld ML20042G1431990-05-0808 May 1990 Forwards WCAP-12588, Sequoyah Eagle 21 Process Protection Sys Replacement Hardware Verification & Validation Final Rept. Info Submitted in Support of Tech Spec Change 89-27 Dtd 900124 ML20042G1001990-05-0808 May 1990 Forwards Proprietary WCAP 12504 & Nonproprietary WCAP 12548, Summary Rept Process Protection Sys Eagle 21 Upgrade,Rtd Bypass Elimination,New Steam Line Break Sys,Medical Signal Selector .... Proprietary Rept Withheld (Ref 10CFR2.790) ML20042G1701990-05-0808 May 1990 Provides Addl Info Re Eagle 21 Upgrade to Plant Reactor Protection Sys,Per 900418-20 Audit Meeting.Partial Trip Output Board Design & Operation Proven by Noise,Fault,Surge & Radio Frequency Interference Testing Noted in WCAP-11733 ML20042G1231990-05-0707 May 1990 Forwards Detailed Discussion of Util Program & Methodology Used at Plant to Satisfy Intent of Reg Guide 1.97,Rev 2 Re Licensing Position on post-accident Monitoring ML20042F7741990-05-0404 May 1990 Informs of Completion of Eagle 21 Verification & Validation Activities Re Plant Process Protection Sys Upgrade.No Significant Disturbances Noted from NRC Completion Date of 900420 ML20042F1691990-05-0303 May 1990 Responds to NRC Bulletin 88-009, Thimble Tube Thinning in Westinghouse Electric Corporation Reactors. Wear Acceptance Criteria Established & Appropriate Corrective Actions Noted. Criteria & Corresponding Disposition Listed ML20042G1381990-04-26026 April 1990 Forwards Westinghouse 900426 Ltr to Util Providing Supplemental Info to Address Questions Raised by NRC Re Eagle-21 Process Protection Channels Required for Mode 5 Operation at Facilities ML20042E9641990-04-26026 April 1990 Forwards Rev 24 to Physical Security/Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML20012E6181990-03-28028 March 1990 Discusses Reevaluation of Cable Pullby Issue at Plant in Light of Damage Discovered at Watts Bar Nuclear Plant. Previous Conclusions Drawn Re Integrity of Class 1E Cable Sys Continue to Be Valid.Details of Reevaluation Encl 1990-09-17
[Table view] |
Text
'
i TENNESSEE VALLEY AUTHORITY '
CHATTANOOGA. TENNESSEE 374ol
$N 157B Lookout Place IFBB 181988 U.S. Nuclear Regulatory Commission '
ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of ) Docket Nos. 50-327 Tennessee Valley Autherity ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) -
ELECTRICAL CALCULATIONS - REVISED FINAL STATUS FOR UNIT 2 RESTART
Reference:
TVA letter to NRC dated June 12, 1987, "Seouoyah Nuclear Plant
, (SQN) - Electrical Calculations - Revised Final Status Report" ;
The purpose of this letter is to update NRC on the status of the electrical calculation program for SQN. It is a supplement to the referenced letter above and will (1) update the status of Condition Adverse to Quality Reports (CAQRs), Significant Condition Reports (SCRs), and Problem Identification Reports (PIRs) written as a result of the calculation program; (2) list new
' calculations performed since issuance of the referenced letter; (3) address the resolution of the unverified assumptions (UVAs); and (4) address postrestart work.
Enclosure 4 of the referenced letter defined a list of commitments to be satisfied by revising all essential minimum sets of calculations before restart. These are discussed below.
- 1. Verification of all previous UVAs.
SQN's Division of Nuclear Engineering (DNE) has addressed this issue by revising all essential minimum sets of calculations required to support '
unit 2 restart to either eliminate the UVA or provide justification in
, the calculation as to its acceptability for restart.
l
- 2. Deletion of nonconservative or unverified design cable lengths.
i calculations were revised to ensure that cable pull card data was utilized instead of design lengths. In the course of this effort, CAQR ,
1 SQP 871629 was written (see enclosure 2, page 6) and is being resolved in i j accordance with Nuclear Engineering Procedure 9.1, "Corrective Action."
The corrective action for unit 2 restart has been completed. I l
l t> o)
' l 1 l 8802220148 880218 l PDR ADOCN 05000328 f
p DCD An Eowai Opportunity Employer
FEB 181988 U.S. Nuclear Regulatory Commission
- 3. Correction of deficiencies identified by the Design Baseline and Verification Program (DBVP).
Calculations have been revised to address punchlist items and CAQRs/SCRs '
generated by DBVP.
4 Incorporation of configurational control (as-constructed) drawings and applicable DBVP walkdown data.
Calculations were revised to include the DBVP walkdown data and marked-up ,
configurational control drawings, t
- Enclosure 1 lists those new calculacions done since the referenced letter was '
a completed. It does not include revisions to the calculations listed in :
l enclosure 2 of that letter. Enclosure 2 of this submittal is a revision to
) enclosure 3 of the referenced letter and updates the status of SCRs, CAQRs, and PIRs In addition. TVA would like to clarify a point that resulted from a question raised by Bechtel Corporation in their enclosure of Employee Concern No. i 213.01. Some calculations are not performed within the Sequoyah Engineering '
Project (SQEP). These calculations, which support relay setting cheets, are l issued by TVA's Power System Operations (PS0) of the Office of Power under their quality assurance program. Although these calculations are performed by PSO, it is the responsibility of the SQEP to review and approve these relay setting sheets before their implementation by PSO personnel for safety-related equipment. SQEP review does not verify the P30 calculation, but looks at these 9etpoints with respect to their impact on safety of the affected ;
system. TVA feels clarification of this point is appropriate in order to '
prevent any misunderstanding between TVA and NRC concerning this item.
i Very truly yours.
4
[
i
] TENNESSEE V LEY AUTHORITY ;
R. Cridley, rector i
! Nuclear Licensing and '
j Regulatory Affairs l
i j Enclosures '
1 cet See page 3 1
I t
1 3
! I
U.S. Nuclear Regulatory Commission FEB 181988 cc (Enclosures):
Mr. K. P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Division Office of Special Projects U.S. Nuclear Regulatory Commission Region II 101 Marietta Street. NW Suite 2900 Atlanta, Georgia 30323 Mr. C. C. Zech. Assistant Director for Projects Mall Stop 7E23 TVA Projects Division Office of Special Projects U.S. Nuclear Regulatory Commission 1920 Norfolk Avenue Bethesda, Maryland 20814
!)equoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy. Tennessec 37379
I ENCLOSURE 1 i ,
I The following are additions to the Instrumentation and Control Calculations t Section. Item 9,, Instrument Setpoint Accuracy Calculations.
1 No. 001B (843 870828 915) . !
l t -
No.,002B (B43 871026 905) l No. 003B (843 860813 901)
No. 004B (B43 860721 903)
No. 006B (B43 870123 901)
No. 70 (B43 870901 914)
No. 71 (B43 870414 904) j No. 72 (B43 870421 903) i No. 73 (B43 870828 913)
! No. 74 (843 871106 906) i No. 75 (B43 870824 909) !
No. 76 (843 87080/ 902) !
. No. 77 (B43 870831 902) l No. 78 (B43 870901 906) ;
No. 79 (843 870709 903)
No. 80 (B43 870914 901) -
No. 81 (B43 870729 904)
No. 82 (B43 870827 907) 4 No. 83 (B43 870901 911) !
No. 84 (843 871001 917)
No. 85 (B43 871009 906) I No. 86 (B43 871012 901) '
! No. 87 (B43 871029 901)
No. 88 (B43 871127 914) i No. 89 (B43 871127 915) i No. 90 (B43 871201 901) !
No. 27S1A l No. 2-FT-70-81A/81E The following are calculations added to their respective item numbers for tux 111ary Power System:
i Item 5 - SQN-E3-011 (DC Voltage Analysis) !
t i
Item 9 - SQN-EPS-011 (Verification of tising Cable Pull !.engths in Voltage I
] Drop Calculations) i l
Item 11 - SQN-APS-004 (Electrical Equipment Ampacity) [
]
Item 14 - SQN-E3-011 (DG Voltage Analysis) !
! The following are calculations added to their respective item number for !
) Control Power System:
l Item 13 - SQN-APJ-010 (Class 1E MCC '.'ndervoltage)
I l Item 26 - SQN-CPS-013 (Cascade Tuse Analysis) i Item 26 - SQN-E3-003 (Class 1E MCC Control Power Transforner overload 1
l Protection) s I
1
)
. ~ _ . - -. _ . . . ._ -_. .. - . - _ _ . - _ - .. . - . _ - . ..
. l l i
'" f ENCLOSURE 2 i I
SEQUOYAH NUCLEAR PLANT (SQN) '
Corrective Action LTst of Condition Adverse'to Quality Reports (CAORs).
- j Significant Condition Resorts (SCRs). and Problem Identification Resorts fPIRs) i i.
l (Sheets 1 to ?). i J t a
Referenced notes for this enclosure (
, are located on the last page t
1 of this enclosure. j
- I a 1 i
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i I
I i I l 1
- I i t
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l
,! A l
l !
r i f 1
- l I !
h 4
I b -
i
- i J I
) l 1
i I
f I l ._.s
SQN - SCRs, PIRs, AND CAQEs FOR ELECTRIC p0WER SYSTEM CALCULATIONS
^
SCR SQNEEB8607R1 PROBLEM: Deficiencies exist with respect to individual components' voltage in the Class 1E auxiliary power system.
CORRECTIVE ACTION: Installation uf eight new cables and eight new 80-percent voltage solenoid valves. En61neering Change Notice (ECN)-L6648 See Note No. 1 SCR SQNEEB8532R3 PROBLEM: Deficiencies exist with respect to individual components' valtage in the 120-V ac vital instrument power system.
CORFECTIVE ACTION: Pulling larger size cable to reduce esbit i.epedance and paralleling supply cables to reduce ,
current through various portions of the affected circuits.
(ECNs-L6609, -L6663 -L6698)
See Note No. 1 SLR SQNEEB8605R1 PROBtEM: Inadequate minimum de input voltage for the unit 1 inverters and 26 miscellaneous solenoid valves at minimum battery terminal voltage.
CORPECTIVE ACTION: Recertification and testing of inverters determined that inverters will operatu properly with Twenty-four solenoids were recategorized available voltage. '
as now-required at minimum battery voltage. The remaining two solenoids were certified operable by the vendor with available voltage. No physical modifications were required. (ECN - N/A)
Closed (B25 870312 101)
SCR SQNEEB8629R4 PROBLEM: Diesel generator potential overload during blackr.ut concurrent with Phase B containment irolation because of random load block addition at T = 30 seconds.
CORRECTIVE ACTION: Addition of time-delay relays to ensure that random loading does not occur simultaneously at T = 30 seconds. (ECN-L6715)
See Note No. 1
- SCR SQNEEB8665RO PROBLEM
- Incorrect setpoints for vital battery boards I, II, '
III, IV, and V main breakers.
CORRECTIVE ACTION: Add redundant protective device or resize existing protective scher.e :.s required by Design Criteria
$QN-DC-V-11.3. (ECN-L6820) l See Note No. 1
. _ . _ _ _ _ _ . - _ _ _ .-_-_.-...._.._.._.._._____._.m ._ _ _ , _ _ _ . _ _ . _ _ . _ - - _ .
i i
el
! l l .
j SCR I 1
SQNEEB8523R0 PROBLEN: Inadequate overcurrent protection for ten V3 '
! penetration circuits. '
j CORRECTIVE ACTION: Add redundant protective device or resize r ex' sting protectiv9 scheme as required by Design Criteria [
] SQN-DC-V-11.3. (ECN-L6606) f I
j c Closed (843 860123 907) I i
I
! SCR j SQNEEB8675R0 PROBLE:1: Inadequate continuous current protection for
- (Unit 1) electrical penetrations. (
i a
SQNEEB8677R0 CORRECTIVE ACTION: Obtain exception to Design Criteria 4
(Unit 2) SQN-DC-V-11.3 for electrical penetrations 52 and 53. !
! (ECN - N/A)
J !
I t
- See Note No. 3 i t
i pIR SQNEEB8657R1 PROBLEM: Fifth vital battery system transfer switches ar- I l not adequately rated to withstand maximum ovallable fault l j current. '
- CORRECTIVE ACTION
- Corrective acticn has not yet been l i detemined. This system is not required for unit 2 restart.
i (ECM - N/A) !
i >
i See Note No. 3
{
j SCR 6
SQNEEB8646R1 PROBLEM: Civen diesel generator breaker closure at 80-percent voltage and 850 r/ min and loads applied at Tao !
(closure of the creaker), the voltage will dip below the !
{
25-percent variance and will not recover +o 90 percent of ;
nominal for 1.9 seconds for blackout with phase A isolation. i
{ CORRECTIVE ACTION: Based upon test results of Surveillance !
Instruction (SI) 7 (performed January .!3.1986), breaker l l closure actually occurs when voltage is greater than '
( 100 percent of nominal. Thus, no deficiency exists and no j l corrective action is required. '
1
- Closed (B25 870220 0,5) i i pIR 4
SQNEEB8666RO PROBLEM: The available fault current at the 6.9-kV unit
) boards exceeds the breaker's ratings for the following
} condition: Full load operation with power supplied from the Unit Service Station Transfomers (USSTs) and generator operating at 24.5 kV (673 MVA available).
90RRECTIVE ACTION: Corrective action was established under j SQ-DCR-p-1958. (ECN-Later) i
- See Note No. 3 I
i j
4
)
1
- _ _ _ ,- _ . , _ _ _- -- ___ . ~ .. _ _ _. _ . , - . _ _ , _ _ _ . _ . . . _ _ _ - _ _ _
SCR SQNEEB86124R0 PROBLEM: Maximum loss of coolant accident (LOCA) loading for control and auxiliary building vent boards 1Al-1, 2Al-A, and 2B1-B' exceeds the feeder breaker continuous current setpoints.
CORRECTIVE ACTION: Change feeder becaker setpoint (proposed). (ECN-L6883)
See Note No. 1 CAQR SQP870791 PROBLEM: The loud tabulations on 125-V de vital battery board single-line drawings 45N703-1R26 and 45N703-2R22 are incorrect relative to de emergency lighting loads.
CORRECT 1VE ACTION: Determine worst-case battery loading and revise calculation SQN-CPS-004 and the affected single-line drawings accordingly (proposed). (ECN-L7186)
See Note No. 1 SCR SQNEEBS6131R0 PROBLEM: Tabulated worst-case 2-hour loading on vital battery boards I, II, III, and IV panel 3 bus exceeds manufacturer's continuous current rating.
CORRECTIVE ACTION: Additional vendor data doeurented a 3-hour bus rating on panel 3 in excess of the 2-hour loading; thus, no corrective action is required.
Closed (B25 871007 019)
SCR SQNEEB86167R3 PROBLEM: This SCR documented three Cans: (1) Lack of selective coordination for 480-V essential raw cooling water (ERCW) boards and diecol auxiliary boards; (2) lack of overload protection for several 480-V IE loads (switchgear and motor control center); and (3) lack of adequate short-circuit protection for station deck su=p purpt A and B.
COIRECTIVE ACTION:
Proposed (1) Adjust breaker long delay pickup; Proposed (2) SCR SQNEEB86167 and PIR SQNEEB86192 identified two deficiencies with respect to thermal overload heaters (TOLS):
A. The TOLS for approximately 100 Class IE motors or valves were not .ized in accordance with the requirements of TVA i
4 Procedutw dethod (PF) 86-18 (TVA).
, B. The impedance of the TOLS for approximataly 100 Class 1E motors or valses proouced excessive voltage drop to the components, thereby potertially rendering the devices inoperable,
i I
a :
As corrective action for the deficiencies, the following }
options were proposed and implemented as appropriate. l A. For motors, resize the TOL in accordance with the I requirements of PM 86-18 and in accordance with position !
C.2 of Regulatory Guide 1.106, revision 1, March 1977. I B. For active valves not actuated by a safety injection (SI) I
, signal, bypass the TOL contacts in accordanca with i ECN-L6883 and technical specification (TS) change 87-29. f C. For SI-actuated valves, bypass the TOL in accordance with
, ECN-L6883 and TS change 87-29. This option in several ,
i cases reduced the circuit impedance significantly and ,
l resulted in the potential for a fault current to exist in '
excess of the associated circuit breaker interrupting rating. In these instances, the circuit breakers were l
j also replaced, ,
For corrective action options 2 and 3, applicable TSs shall -
be revised as required, f l
Proposed (3) Replace thermal magnetic breakers. i See Note No. 1 l PIR
, SQ:lEEB8668 PROBLEM: Pressure switches are not qualified to seismic l j category 1 requirements. Failure of these switches will !
i cause the Main Control Room (MCR) air chillers to not perform e i their intended safety function. !
! CORRECTIVE ACTION: Replace components or obtain seismic l
}
- l qualification for existing components. >
j Seismic qualification obtstned in accordance with j
- calculation SQEP-EMC2, "Seismic Qualification of Alarm Relay
Power Supply and Pressure Transmitters." No further action E
- required.
I !
., PIR PROBLEM: An interlock from the carbon dioxide (CO ) fif*
2 I
- SQNEEB8628R0 protection system initiation signal that stops the diesel [
j generator room exhaust system is not seismic category 1 as ,
i required by the Final Safety Analysis Report (TSAR), !
I section 9.4.5.3. I
.i ;
CORRECTIVE ACTION: Replace components or obtain seismic
- qualification for existing components. (ECW - Later) 1 See Note No. 3 I l
- 1 1
1
l i
s j PIR 3
SQNEEB8683R0 PROBLEH: Heater control circuits are not seismically qualified. Their f ailure can cause the heaters to turn on inadvertently, with the potential to heat the associated roots to an. unacceptable temperature. '
, g0RRECTIVE ACTION: Replace components or obtain seismic qualification for existing components. (ECH - Later)
I
' See Note No. 3 (Item has been transferred to the Mechanical Engineering Branch (MEB]).
! l SCR '
SQNEEB8667R0 PROBLEM: Air compressors were seismically qualified; however, qualification did not demonstrate that instrument
} setpoints would not have an unacceptable shift following a :
i seismic event, j CORRECTIVE ACTION: Replace components or obtain seismic
) qualification for existing components. (ECN-L6878) r See Note No. 1 o
! l SCR
! SQNEEB8673R0 PROBLEMt High temperature shutdown interlock in either j shutdown board room A or B will shut down the l air-conditioning equipment for the opposite training board j room.
1 CORRECTIVE ACTION: Purther evaluation of system design has determined that problem does not exist.
l i Closed (B25 870404 106) i i i l SCR i
- SQNEEB8691R0 PROBLEM: A. pres'nt setpoint for instruments that start the traveling screen motors for the ERCW system is 90 PSIC.
I '
! Accuracy of these instruments is i 4.5 PSIG. Safety limits !
?
' are lower = 70.5. upper . 70.9. Therefore, operational ;
limits are violated even with a setpoint change. l i Corrective Acti;n: Leave the setpoint at 90 PSIC. Change !
' the logic diagram as appropriate. Establish a yearly i surveillance requirement to censure the screen wash pump discharge pressure and river level. The upper operational ,
limit can be determined by using the equation given in l l "Su mary of Calculated Data" in DNE calculation. I "Demonstrated Accuracy Calculation." O-PS-67-471. revision 0 t
(843 870120 935). Initiate corrective action if the 4
discharge pressure falls below this upper limit.
t i PROBLEN: B. present setpoint for the ERCW backwash initiation is 2.0 PSID increasing; operational limit is 0.5 PSID. Therefore, the present setpoint violates the operational limit.
l CORRECTIVE ACTION: Setpoints must be changed. (ECN-L7291 l and -L7292).
I J
i i
________.________.____I
. i I 6-l
}
PROBLEM: C. Present setpoint for the ERCW backwash flush j
] initiation is 20.0 PSID increasing. Operational limit is i 34.0 PSID decreasing. Functional logic is incorrect, and {
! setpoint is in violation of operational limit, j CORRECTIVE ACTION: Setpoint must be changed, and operational limits need to be recalculated. (ECW-L7291 and -L7292) (
4 i
See Note No. 3 !
I I l SCR j SQNEEB8689R0 PROBLEM: A. Present setpoint for nonessential control air j
) isolation is 80 PSIG decretainst system design limit is j 83 PSIC. Instrument accuracy is 1,2.7 PSIC. l 4
CORRECTIVE ACTIOM: Reevaluate mechanical system design t limits and revise setpoint, if required. (ECN-L6878) !
i !
j PROBLEM: B. Present setpoint for starting and loading the l
{ essential air compressors is 75 PSIC decreasing; system i
) design limit is 73 PSIG. With insecuracles of 2.7 PSI.
system design limits could be violated.
]
1 CORRECTIVE ACTION: Reevaluate mechanical system design ,.
j limits and revise setpoint, if required. (ECN-L6878) (
l See Note No. 1 lt SCR SQUEEB8690R0 PROBLEM: A. The automatic control for the turbine-driven I feedwater pump is set for 880 gal / min. The setpoint to lock j out manual control is 800 gal / min or greater. Therefore, t i manual control is effectively presented. Operating i i procedures require manual control. i i CORRECTIVE ACTION: None. Reevaluated system operation with i i respect to design criteria and determined that a problem did f l not exist. (ECN - N/A) i PROBLEMt B. FS-46-57 has a reset adjust that must be set to f minimum to prevent lockup. EIs do not require this adjustment to be made.
CORRECTIVE ACTION: None. Reevaluated system operation with I I respect to design criteria and determined that a problem did {
not exist. (ECN-N/A) !
i
! Closed (B25 870928 024) !
CAQR SQP871608 PROBLEM: Required accuracy for the refueling water storage I l tank level Postaccident Monitoring (PAM) indicators is
) violated. {.
? CORRECTIVE AC.I1QN Recalibrate transmitter and revise SI to i require the equipment to be checked at a maximum frequency of l 18 months. f
, i-See Note No. 2 l I
4 I _ __ _ _ ___I
CAQR SQP871629 PROBLEM: Cable pull cards are not quality assurance documented.
CORRECTIVE ACTION: Perform a voltage sensitivity analysis by determining,the allowable voltage drop margin between the calculated voltage at the device terminals and the voltage required for device operation. Field is to verify those cable lengths where margin is nat significant (less than 70 percent). This item is required for unit 2 restart.
See Note No. 1 CAQR SQP871631 PROBLEM: Voltage drop calculation for the "diation monitoring equipment shows that the voltago .* quired to start equipment is below manufacturer recommendations.
CORRECTIVE ACTION: Prepare exception request for design criteria.
See Note No. 3 CAQR SQP871644 PROBLEM: The satpoints for the upper head injection level switches are inaccurate.
CORRECTIVE ACTION: The corrective action has been determined and will be issued and implemented after unit 2 restart. It was determined that the description of the CAQR did not apply to unit 2 restart.
See Note No. 3 NOTES:
- 1. The corrective actions for this CAQ/CAQR have been identified and implemented for unit 2. The design and fieldwork are coeplete for that portlon of the corrective action that is required for unit 2 restart. The remaining work that is required has been scheduled so a unit 2 postrestart item.
- 2. The corrective actions for this CAQ/CAQR have been identified and are scheduled as unit 2 restart items. The implementation of that portion that is required for unit 2 restart will be completed before restart; all remaining work will be scheduled accordingly.
- 3. The corrective actions for this CAQ/CAQR have been generally identified and are scheduled as postrestart items. The corrective action has been scheduled accordingly.