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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
.l TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ot SN IS7B Lookout Place DEC 29 886 Director of Nuclear Reactor Regulation Attention: Mr. B. Youngblood, Project Director PWR Project Directorate No. 4 Division of Pressurized Water Res clors (PWR)
Licensing A U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Youngblood:
In the Matter of . ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT - ELECTRICAL CALCULATIONS - FINAL STATUS REPORT This transmittal completes the electrical calculations for Sequoyah Nuclear
. Plant unit 2 rectart. An entire set of calculations is contained in enclosure
- 3. Revisions and rationale are noted in the format sheet that preceeds each calculation. In addition, there are bars in the page margin to indicate changes from previous submittals. The Sargent and Lundy (S&L) final report, "Sequoyah Nuclear Plant Electrical Calculation Program Assessment" (April 8, 1986), and the TVA Electrical Engineering Branch Policy Memorandum PM86-02 jointly and fully define the electrical power system calculations required to support the design bases of a standardized nuclear plant. These two documents define subsets of the calculations which are specifically required to support Sequoyah unit 2 restart. These calculations consist of auxiliary power, control power, instrumentation and control, and raceway calculations. With the exception of the required raceway calculations which shall be addressed in subsequent cable issue submittals (ampacity and bend radii), enclosure 1 documents that all required sequoyah unit 2 restart calculations are essentially complete. Enclosure 1 lists the required electrical power system
[d[ 3'f calculations from the S&L final report and requirements from the TVA Electrical Engineering Branch Policy Memorandum. These are correlated with
=_ -the electrical calculation contained in enclosure 3. >
g9 g .[ Further revisions to these calculations are required to (1) verify all e if previously " unverified assumptions " (2) document conformance to
- .M "as-constructed" electrical drawings and applicable design baseline ghi ~ ~ ~
verification program walkdown data, and (3) support modifications identified in engineering change notices and field change requests. Activities (1) and (2) shall be complete before unit 2 restart. Activity (3) is a maintenance effort and shall continue indefinitely. The Sequoyah Electrical Calculations Program identified several conditions adverse to quality. These are summarized in enclosure 2 along with the required / proposed corrective action.
Enclosure 3 contains the text of each required unit 2 restart calculation. In p
h I An Equal Opportunity Employer jl[ .
r
.2-Director'of Nuclear Reactor Regulation ElEC 291996 summary. .wlth the exception of continuing verification programe as noted above the Sequoyah Electrical Calculations Program is presently r,umplete with respect to Sequoyah unit 2 restart calculations. All required calculations
~
3 have.been performed and all conditions adverse to quality are identified for corrective action.
- Due'to the size of the electrical calculations listed in enclosure 3, one copy of the calculations has been sent directly to_'the NRC re' viewer, Peter Kang.
If you have any questions regarding this final status report, please get in touch with Mark Burzynski at (615) 870-6172.
Very truly yours, TENNESSEE VALLEY AUTHORITY h
).61.&mn p.Gridley, Director Nuclear Safety and Licensing Enclosures cc (Enclosures):
_U.S. Nuclear Regulatory Commission Region II Attn: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta. Georgia 30323 Mr. Carl Stahle Sequoyah Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Mr. G. G. Zech, Director TVA Projects U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
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ENCLOSURE 1 Restart Systems s&L and TVA Electrical Branch Tables t
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S:rgent & Lundy Assessment TVA' Policy Memorandum- TVA Electrical. Calculation (d); -
Armiliary Power Calculations -PN86-02 (EEB)
Required for Restart B43 860508 902
- 1. Power Cable Sizing 9. Power Cable Sizing 1. . .
- c. Ampacity a. To be addressedfin cable-issues. submittal!
- b. Voltage Drop b. OE2-EEBCALOO1J
- c. Short-Circuit Withstand c. D2SDJ-P213350, D2SDJ-P213350-3, SQN-APS-003
- 2. PO2Gtration Sizing 10. Penetration-Sizing 2.
- o. Maximum Short Circuit a. OE2-DS196RP
- b. Continuous Current b. SQN-EPS-002
- c. Overload (STOL)~ C. SQN-EPS-004
- 3. Auxiliary System Loading ,
- 11. Auxiliary System Load Flow 3. OE2-EEBCAL001
, 4. Auxiliary System Voltages 12. Auxiliary System Voltare 4. OE2-EEBCAL001 Profile 1
- 5. Auxiliary System Short Circuits 13. Auxiliary System Short 5. EN2-DS192RP, D2SDJ-P213350-1 Circuit A alysis
- 6. Diesel Generator Performance 14. Diesel Generator 6. SQN-E3-002*
Performance
- 5. Diesel Generator Sizing l
1
. 7. Bus Transfer 15. Bus Transfer Tests and j Analysis 7. SQN-E3-002 i
' 8. 480V Class IE Switchgear Protection 17, 480V Class IE Switchgear 8. SQN-APS-003, D25DJ-P213350-1, Selection, Protection, and D245-DS199RP, D2SDJ-P213350 Coordination i
j 9. 480V Class IE Motor Control Center 19. 480V Class IE Motor Conrol 9. SQN-APS-003, D2SDJ-P213350 1, Protection Center Selection, D245-DS199RP, D2SDJ-P213350 Protection, and Coordination l
- 10. Submerged Equipment Analysis 20. Submerged Equipment 10. D245-DS199RP J ,
Analysis i
)11.AppendixRAssociatedCircuit 22. Appendix R Associated 11. D2SDJ-P213350, D2SDJ-P213350-3
-l Analysis Circuit Analysis
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O o Fcr SQN unit 2 restart, only the following conditions required evaluation:
(1) Loss of offsite power (80)
(2) B0 concurrent with Safety Injection Signal (SI)' containment isolation phase A (3) B0 concurrent with SI containment isolation phase B.
O'nly modifications required for these three conditions will be porformed prior to unit 2 restart.
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Sargent & Landy Assessment -TVA Policy Memorandum'. TVAElectricaldalculation(s)l -
Cratrol Power calculations ~
PN86-02 (EEB)-
f Required for Restart 843.860508 902 i
! .m i - 1. Electrical Penetration Sizing .8.-Electrical; Penetration' 1.
j o. Maximum Short Circuit. . Sizing.and Protection -
a.- SQN-NV3-PEN-1,:SQN-EPS-003 .
j b. Continuous Current b. SQN-EPS-002
- c. Overload (STOL) c. SQN-EPS-004
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- 2. Low Voltage AC Power Cable Sizing 11. Low Voltage AC Power 2. .
! o. Ampacity Cable Sising a. To be addressed'in cable issues submittal
- b. Voltage Drop b.- SQN-VD-VAC-1,2, and 3 i c. Short-Circuit Withstand , c .~ SQN-APPR-1,2' i
! 3. DC Power Cable Sizing 12. DC Power-Cable Sizing 3. ;
l o. Ampacity a. To be addressed in cable. issues' submittal i b. Voltage Drop fb. SQN-VD-VDC-1 and~2
! c. Short-Circuit Withstand c. SQN-APPR-1,2
- 4. Centrol Cable Sizing 13. Control and Instrumentation 4.
t c. Ampacity Cable Sizing a. To be addressed in cable issues submittal
- b. Voltage Drop b. SQN-VD-VAC-1, 2, 3 and SQN-VD-VDC-1,2 l c. Short-Circuit Withstand
- c. SQN-APPR-1,2 i 5. Class IE AC System Loading 14. Class IE.AC System 5. SQN-CPS-005 Load Flow 4
- 6. Class IE DC System Loading 16. Class IE DC System 5. SQN-CPS-004
- Load Flow -
1 l 7. Class IE AC System Voltages 18. Class IF AC System 7. SQN-VD-VAC-1,2,3
- Voltage Profile l
8.
. Class IE DC System Voltages 20. Class IE DC System 8. SQN-VD-VDC-1,2 '
i Voltage profile i
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TVA Riectrical Calculation (s)'
Sergent & Lun'dy Assessment' TVA Policy Namorandums .
C:strol' Power Calculations PN86-02 (EEB)
Required for Restart 543 860508 902
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- 9. C1ces IE AC System Short-Circuit
'22. Class IE AC System '9. SQN-APPR-1,2 (Appendix R' Calculations)'
Short-Circuit Analysis .
Carrents
- 26. Class IE AC System SQN-NV3-PEN-1, SQN-EPS-003 (Penetrations)-
Selection, Protection, and Coordination
- a. SQN-CPS-003:
a.-Withstand / Interrupting Ratings b. SQN-CPS-006.
- b. Inadvertent Breaker Tripping 24..Clast IE DC System fl0. SQN-APPR-1,2 (Appendix R Calculations)..
- 10. C1 css IE DC System Short-Circuit Short-Circuit Analysis Currents 28. Class IE DC System SQN-NV3-PEN-1, SQN-EPS-003'(Penetrations)'
Selection Protection, and Coordination
- a. Withstand / Interrupting Ratings a. SQN-CPS-003
- b. Inadvertent Breaker Tripping b. SQN-CPS-006
- 11. C1 css IE Battery Recharging Time 3. Vital Battery Sizing 11. SQN-CPS-004
- 5. Vital Battery Charger SQN-CPS-004 .
Sizing .
- 12. Class IE AC System Protection Same as S&L Item 9 12. Same as Item 9
- 13. Class IE DC System Protection Same as S&L Item 10 13. Same as Item 10
- 30. Battery Hydrogen 14. 2-HYDROGO-1 EEB 841226 926
- 14. Battery Hydrogen Generation Generation
- 15. Submerged Equipment Analysis 31. Submerged Equipment 15. SQN-SBNG-1 Analysis
- 32. Appendix R Associated 16. SQN-APPR-1,2
- 16. Appendix R Associated Circuit -Circuit Analysis Analysis DNE1 - 1663W H of 0
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TVA Policy Nemor ndum ,- TVA Electrical' Calculation (s) -
y Icarumentation-& Control Calculations- PN86-02 (EEB)
Required for Restart B43 860508 902'
~
- 1. 46-1 (B43 860826 901).
- 1. Flow Element Calculations 1. Flow Element Calculations
'46-4 (B43 860915 917)~
- 2. HVAC Airflow Nessuring Station 2. HVAC Airflow Nessuring- 2. 46-2 (843 860826 902)
-Station
- 3. Sample Line Calculations 3. Sample Line Calculations 3. Not Applicable'(N/A): No safety-rel'ated sample lines required for U2' restart. .
~
- 4. Sample Cooler Size Calculations 4. Sample Cooler Size 4. N/A: 'No safety-related coolers required'for U2 restart
- 5. Isskinetic Nozzle Calculations 5. Isolkinetic Nozzle 5. 46-2 (B43 860826 902)
- 6. Centrol Valve, Relief Valve, 6. Control Valve, Relief. 6. 46-8 (843 860917.912)
Pressure Regulator Size Valve, Pressure Regulator Size
'7. Hsct Trace Calculations 7. Heat Trace Calculations 7. 46-3 (B43 860912 902)
- 8. Centrol Loop Calculations 8. Control Loop Response Time 8. 46-5 (B43 860915.925) and Stability Calculations
- 9. Instrument Cable Design 9. Cable leakage was addressed, where applicable, in individual instrument accuracy' calculations.
Calculations -
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S:rgent & Lundy Assessment _.
TVA Policy Memorandum 'TTA Electrical Calculation (s)I ^
V Issrumentation & Control Calculations- .PN86-02 (EE,5)
-R;guired for Restart B43.860508 902 ,
4
- 10. S:tpoint and Accuracy Calculations 9. Setpoint and Accuracy ;9. # 1 (843 860809 902)
Calculations # 2.(843 860809 901)
- # 3 (843 860807 904)
- 4 (B43'8510291919)
> .# 5 (843 860917.916)
, # 6 (843 851029 921)
- 7 (843 860813 906)
- 8 (B43 868059 913)
- 9 (B43 860917 917)
- 10 (B43 860917 918)
{ #11 (B43 860805 910) 4 #12 (B43 860805 911)
I #13 (B43 85805 912) i #14 (B43 860512 913)
- 15 (843 860512 914)
I
- 16 (B43 860501 905) l #17 (B43 860920 908)
! #13 (B43 85805 912)'
! #14 (B43 860512 913)
! #15-(843 860512 914) l #16 (B43 860501 905)
{ #17 (B43 860920 908)
- 18 (B43 860917 915)
! #19 (B43 860107 922)
- 20 (B43 860107 925)
! #21 (B43 860507 904)
- #22 (B43 860507 903)
! #23 (B43 850102 911) i #24 (B43 851217 907)-
1 #25 (B43 860917 920) l #26 (B43 851205 908)
- 27 (B43 860805 914)
- 28 (B43 850830 903)L i #29 (843 860917 919)
- #30 (843 861104 918) i a
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Setpoint and Accuracy Calculaticas 9. Setpoint and Accuracy #31 (843 861106'903)-
Calculations #32 (843 851118 918)
- 33 (843 851118 919)
.#34_(B43 860630 902)-
- 35 (B43 860221 903)
- 36 (843 860827 907)
- 37 (B43-860827.908). .
- 38 (843 860228 901)
- 39 (B43 860206 906)
- 40 (B43 860206 907)
- 41 (B43 862516 907)
- 42 (843 861003 901)
- 43 (B43 860624 914).
. #44 (B43 860805 901)
- 45 (B43 860820 902)
- 46 (B43 860829 917)
- 47 (B43 860915 910)
- 48 (343 860915 912)
- 49 (B43 860915 914)
- 50 (843 860915 914)
- 51 (B43 860915 915)
- 52 (843 860915 916)
- 53 (B43 860917 911)
- 54 (B43 860917 913)
- 55 (B43 861022 901) k s
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'S:rgent & Lundy Assessment .
TVA Policy Nemoranden TVA Electrical Calculation (s)
Icarumentation & Control Calculations PN86-02 (EEB)
Required for Restart B43 860508 902
- 11. Cutrol and Essential Air System' ;10. Control and Essential 11. NEB Calculation 843'861014 904' Calculations . Air System Calculations
- 12. Isotrument Sense Line Size 11. Instrument Sense Line 12 46-6 (B43 86106 904)~
Size Justification
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- 13. Elcetrical Penetrations 12. Electrical Penetrations 13. Addressed in SQN-NV3-PEN-1 and Design Criteria SQN-DC-V-11.3
- 14. S2p ration Justification 13. Separation Justification 14. N/A: This issue was addressed, where applicable, by individual NCRs/SCRs.
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I g CAQ/SCR/ Corrective Action Summary b
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SHEET 2/7 SCR-SONEEB8665.- PROBLEM: INCORRECT SET POINTS FOR VITAL BATTERY BOARDS 1, 11, 111, IV, AND V MAIN BREAKERS.
CORRFCTIVE ACTION: RESET MAIN BREAKERS LONG DELAY SETTING.
SCR SONEEB8523 - PROBLEM: INADEQUATE OVERCURRENT PROTECTION FOR
' TEN V3 PENETRATION CIRCUITS.
CORRFCTIVE ACTION: ADD REDUNDANT PROTECTIVE DEVICE OR RESIZE EXISTING PROTECTIVE SCHEME AS REQUIRED BY DESIGN CRITERIA SQN-DC-V-11.3.
- SCR .
SQNEEB8676 - PROBLFM: INADEQUATE CONTINUOUS CURRENT PROTECTION
'(UNIT- 1)- FOR ELECTRICAL PENETRATIONS.
SONEEB8677 CORRrCTIVE ACTION: OBTAIN EXCEPTION TO DESIGN (UNIT 2)
CRITERIA SQN-DC-V-11.3 FOR ELECTRICAL PENETRATIONS 52 AND 53.
PIR SQNEEB8657 - PROBtFM: FIFTH VITAL BATTERY SYSTEM TRANSFER
" SWITCHES ARE NOT ADEQUATELY RATED TO WITHSTAND MAXIMUM AVAILABLE FAULT CURRENT. 4 CORRECTIVE ACTION: CORRECTIVE ACTION HAS NOT YET BEEN DETERMINED. THIS-SYSTEM IS NOT REQUIRED FOR UNIT 2 RESTART.
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SHEET 3/7 SCR g
SONEEB8646 - PROBLEM: GIVEN DIESEL GENERATOR BREAKER CLOSURE +=0 AT 80% VOLTAGE AND 850 RPM AND LOADS APPLIED AT (CLOSURE OF THE BREAKER), THE VOLTAGE WILL DIP BELOW THE 25% VARIANCE AND WILL NOT RECOVER TO 90%
OF NOMINAL FOR 1.9 SECONDS FOR BLACK 0UT WITH PHASE O IcTION: BASED UPON TEST RESULTS OF g SI 7 (PERFORMED 1/23/86) BREAKER CLOSURE ACTUALLY OCCURS WHEN VOLTAGE IS GREATER THAN 100% OF d NOMINAL. THUS, NO DEFICIENCY EXISTS AND NO CORRECTIVE ACTION IS REQUIRED.
PIR j SQNEEB8666 - PROBLEM: THE AVAILABLE FAULT CURRENT AT THE 6.9KV UNIT BDS EXCEEDS THE BREAKERS' RATINGS FOR THE FOLLOWING CONDITION:
FULL LOAD OPERATION WI1H F0WER SUPPLIED FROM THE USST'S AND GENERATOR OPERATING AT 24.5KV (673 MVA AVAILABLE).
CORRECTIVE ACTION: CORRECTIVE ACTION WAS ]
ESTABLISHED UNDER SQ-DCR-P-1958.
SCR SQNEEB86124 - PROBLEM: MAXIMUM LOCA LOADING FOR C&A BLDG VENT BDS 1Al-1, 2Al-A, AND 2B1-B EXCEEDS THE FEEDER BREAKER CONTINUOUS CURRENT SETPOINTS.
CORRECTIVE ACTION! CHANGE FEEDER BREAKER h y
SETPOINT (PROPOSED).
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SHEET 4 /'7 SCR-
-SONEEB86131 PROBLEM: TABULATED WORST CASE 2-HOUR LOADING ON
+: ' VITAL BATTERY BOARDS 1, II, III, AND IV PANEL 3 BUS' EXCEEDS MANUFACTURER'S CONTINUOUS CURRENT
' RATING.
CORRECTIVE ACTION: ADDITIONAL VENDOR DATA DOCUMENTED A 5 HOUR BUS RATING ON PANEL 3 IN EXCESS OF THE 2 HOUR LOADING: THUS, NO CORRECTIVE ACTION IS REQUIRED.
SCR SONEEB86167 - PROBLEM: THIS SCR DOCUMENTED THREE CAQS: (1) LACK p 0F SELECTIVE COORDINATION FOR 480V ERCW BDS AND p! DIESEL AUX BDS; (2.) LACK OF OVERLOAD PROTECTION
/ FOR SEVERAL 480V 1E LOADS (SWGR & MCC); (3) LACK OF ADEQUATE SHORT-CIRCUIT PROTECTION FOR STATION DECK SUMP PUMPS A AND B.
CORRECTIVE ACTION: (PROPOSED) (1) ADJUST BREAKER LONG DELAY PICKUP; (2) REPLACE AND/0R ADD THERMAL OVERLOADS (:: 160); (3) REPLACE THERMAL MAGNETIC BREAKERS.
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saecr 5/7 PIRS AND SCRS FOR INSTRUMENTATION AND CONTROL SYSTEM CALCULATIONS PIR SQNEEB8668 - ER011LEM: PRESSURE SWITCHES ARE NOT QUALIFIED TO SEISMIC CATEGORY l REQUIREMENTS. FAILURE OF THESE SWITCHES WILL CAUSE THE MCR AIR CHILLERS NOT TO PERFORM THEIR INTENDED SAFETY FUNCTION.
CORRECTION ACTION: REPLACE COMPONENTS OR OBTAIN SEISMIC QUALIFICATION FOR EXISTING COMPONENTS.
PIR SONEEB8682 - PROBLEM: AN INTERLOCK FROM THE CO21 FIRE PROTECTION SYSTEM INITIATION SIGNAL THAT STOPS THE DIESEL GENERATOR ROOM EXHAUST SYSTEM IS NOT SEISMIC CLASS 1 AS REQUIRED BY FSAR SECTION 9.4.5.3.
CORRECTIVE ACTION: REPLACE COMPONENTS OR OBTAIN SEISMIC QUALIFICATION FOR EXISTING COMP 0NENTS.
PIR SQNEEB8683 - PROBLEM: HEATER CONTROL CIRCUITS ARE NOT SEISMICALLY QUALIFIED. THEIR FAILURE CAN CAUSE THE HEATERS TO TURN ON INADVERTENTLY, WITH THE POTENTIAL TO HEAT THE ASSOCIATED ROOMS 10 AN UNACCEPTABLE TEMPERATURE.
CORRECTIVE ACTTQN: REPLACE COMPONENTS OR OBTAIN SEISMIC QUALIFICATION FOR EXISTING COMPONENTS.
'y SCR SONEEB8667 - PROBLEM: AIR COMPRESSORS WERE SEISMICALLY
.' QUALIFIED; HOWEVER, QUALIFICATION DID NOT DEMONSTRATE THAT INSTRUMENT SETPOINTS WOULD NOT HAVE AN UNACCEPTABLE SHIFT FOLLOWING A SEISMIC EVENT.
CORRECTIVE ACTION: REPLACE COMPONENTS OR OBTAIN SEISMIC QUALIFICATION FOR EXISTING COMP 0NENTS.
SCR SONEEB8673 - PROBLEM: HIGH TEMPERATURE SHUTDOWN INTERLOCK IN EITHER SHUTDOWN BOARD ROOM A OR B WILL SHUT DOWN THE AIR CONDITIONING EQUIPMENT FOR THE OPPOSITE TRAINING BOARD ROOM.
CORRECTIVE ACTION: CONTROL SCHEME MUST BE REVISED.
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SCE:SQNEEB8691 -
PROBLM:
A.1"PRESENT 4ETPOINT'FOR INSTRUMENTS THAT START THE u-TRAVELING SCREEN HOTORS-FOR THE ERCW SYSTEM IS 90 L
PSIG. ACCURACY OF THESE INSTRUMENTS IS i 4.5 PSIG.
,l '- SAFETY LIMITS ARE LOWER = ~10.5, UPPER = 70.9.
TMEREFORE, OPERATIONAL LIMITS ARE VIOLATED EVEN WITH A '
SETPOINT CHANGE.
B. PRESENT SETPOINT FOR THE BRCW BACKWASH INITIATION IS 2.0 PSID INCREASING; OPERATIONAL LIMIT IS 0.5 PSID.
'THEREFORE, THE PRESENT SETPOINT VIOLATES TIIE i OPERATIONAL LIMIT.
CORRBCTIVE ACTION: SETPOINTS MUST BE CHANGED PROBLEM:
-C. -PRESENT SETPOINT FOR THE ERCW BACKWASH FLUSH INITIATION IS 20.0 PSID INCREASING. OPERATIONAL LIMIT
. IS-34.0 PSID DECREASING.- FUNCTIONAL LOGIC IS
-INCORRECT AND SETPOINT IS'IN VIOLATION OF OPERATIONAL LIMIT.,
CORRBCTIVE ACTION: SETPOINT MUST BE CHANGED AND-
' OPERATIONAL LIMITS NEED TO BE RECALCULATED.
SCR HQNEBB8684 -PROBLIRt: - PRESENT SETPOINT AND SAFETY
~
LIMIT FOR THE RCS TO RHR LETDOWN LINE PIPE RUPTURE DETECTION ARE BOTH 1250F. ANY INSTRUMENT INACCURACY HILL CAUSE THE ENVIRONMENTAL LIMIT TO BE VIOLATED.
CORRBCTIVE ACTION: SBTPOINTS MUST BE CHANGED s SCR SQNEEB8689 -
PROBLEM:
A. PRESENT SETPOIM <OR NON ESSENTIAL CONTROL AIR ISOLATION IS 80 kSIG DECREASING; SYSTEM DESIGN LIMIT IS 83 PSIG. INSTRUMENT ACCURACY IS i 2.7 PSIG.
CORRECTIVE ACTION: RiEVALUATE MECHANICAL SYSTEM DESIGN LIMITS AND REVISE SETPOINT, IF REQUIRED.
PROBI,BM:
- B. PRESENT SETPOINT FOR STARTING AND LOADING Tile ESSENTIAL AIR COMPRESSORS IS 75 PSIG DECREASING,
' SYSTEM DESIGN LIMIT IS 73 PSIG. WITH INACCURACIES OF I 2.7 PSI, SYSTEM DESIGN LIMIT COULD BE VIOLATED.
CORRECTIVE ACTION: REEVALUATE MECHANICAL SYSTEM DESIGN LIMITS AND REVISE SETPOINT, IF REQUIRED.
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SHGET 7/7 SCR SQNEEB8690 -
U PROBI,IDE:
A. 'THE AUTOMATIC CONTROL'FOR THE TURBINE DRIVEN F.W." PUMP -
IS SET FOR 880 GPM. THE SETPOINT TO LOCK OUT MANUAL CONTROL IS 880 GPM OR GREATER. THEREFORE, MANUAL CONTROL IS EFFECTIVELY PRESENTED. OPERATING PROCEDURES REQUIRE MANUAL CONTROL.
CORRECTIVE ACTION: NONE. REEVALUATED SYSTEM OPERATION WITH RESPECT.TO DESIGN CRITERIA AND DETERMINED THAT A PROBLEM DID NOT. EXIST.
PROBLEM:-
B. FS-46-57 HAS A RESET ADJUST WHICH MUST BE SET TO MINIMUM TO PREVENT LOCK-UP. SURVEILLANCE INSTRUCTIONS DO NOT REQUIRE THIS ADJUSTMENT TO.BE MADE.
' CORRECTIVE ACTION: NONE. REEVALUATED SYSTEM OPERATION WITH RESPECT TO DESIGN CRITERIA AND DETERMINED THAT A PROBLEM DID NOT EXIST.
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ENCLOSURE 3 Electrical Calculation
- ;- LAuxiliary Power Calculations Control Power Calculations B43 861124 906 B43 861219 904 B43 861210 902- _
B43 861219 905
. B43 861003'904 B43 851028 901 B25 860619 803: B43 860929 901 B43 860813 914 .B43 860210 925
- B43 860703 925 B25 860804 103
~B43 861006 901~ B43 861002 901 B43 861202'901' B43 860801607
-B43 851231 930 -B43 860808 905 B43 861210 909 B43 860829 926 B43 861222 902 EEB 850111 909 B43 860815 901 B43 861110 901 B43 861110 902 B43 860919 903 B43 860801 604 B43 860801 605 B43 861203 902 B43 861210 901 ,
B43 861210 903 I&C CALCULATIONS B43 860809 902 B43 860507 904
,B43 860423 917 B43 860507 903 B43 860809 901 EEB 850102 911 B43 860619 901 B43 851217 907
.B43 860807 904 B43 860917 920 B43 851029 919 B43 851205 908 B43 860721-903 B43 860805 914 B43 860917 916 B43 850830 903 B43 851029 921 B43 860917 919 B43 860813 906 B43 861104 918 B43 860805 913 B43 861106 903 ' --
B43 860917 917 B43 851118 918
'B43 860917 918 B43 851118 919 B43 860805 910 B43 860630 902 B43 860805 911 B43 860221 903 B43 860805 912 B43 860827 907
y n' . i
,e I&C CALCULATIONS EM3 860512 913 B43 860827 908 f - '
'B43_860512 914 B43 860228 901 B43 860507 905- B43 860206 906 B43 860820 908 B43 860206 907 B43 860917;915 B43 861217 912 B43 860107 922. B43 861003 901 B43 860107'925 B43 8()624 914 B43 860805 901 B43 860915 910 B43 860820 902 B43 860915 912 B43 860826 901 B43 860915 913 B43 860826 902' B43 860915 914
-B43.860912 902 B43 860915 915 B43 860915 917 .B43 860915 916 a B43 860915 925 B43 860917 911
-B43 861106 904 B43 860917 913
-B43 860829 917 B43 861022 901
.B43 860917 912 l
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SCR SQNEEB8691 -
PROBLEM:
.A. .PRESENT SETPOINT FOR INSTRUMENTS THAT START THE
' TRAVELING SCREEN MOTORS FOR THE ERCW SYSTEM IS 90 ',
PSIC. ACCURACY OF THESE INSTRUMENTS IS % 4.5 PSIC.
SAFETY LIMITS ARE LOWER = 70.5, UPPER = 70.9.
THEREFORE, OPERATIONAL LIMITS ARE VIOLATED EVEN WITH A SETPOINT CHANGE.
B. PRESENT SETPOINT FOR THE ERCW BACKWASH INITIATION IS 2.0 PSID INCREASING; OPERATIONAL LIMIT IS 0.5 PSID.
THEREFORE,'THE PRESENT SETPO!NT VIOLATES THE OPERATIONAL LIMIT.
-CORRECTIVE ACTION: SETPOINTS MUST BE CHANGED PROBLEM:
C. PRESENT SETPOINT FOR THE ERCW BACKWASH FLUSH INITIATION IS 20.0 PSID INCREASING. OPERATIONAL LIMIT IS 34.0 PSID DECREASING. FUNCTIONAL LOGIC IS INCORRECT AND SETPOINT IS IN VIOLATION OF OPERATIONAL LIMIT.
CORRECTIVE ACTION: SETPOINT MUST BE CHANGED AND OPERATIONAL LIMITS NEED TO BE RECALCULATED.
SCR WQNEEB8684 -PROBLEM: PRESENT SETPOINT AND SAFETY LIMIT FOR THE RCS TO RHR LETDOWN LINE PIPE RUPTURE DETECTION ARE BOTH 1250F. ANY INSTRUMENT INACCURACY
.WILL CAUSE THE ENVIRONMENTAL LIMIT TO BE VIOLATED.
CORRECTIVE ACTION: SETPOINTS MUST BE CHANGED.
SCR SQNEEB8689 -
PROBLEM:
-A. PRESENT SETPOINT FOR NON ESSENTIAL CONTROL AIR ISOLATION.IS 80 PSIG DECREASING; SYSTEM DESIGN LIMIT ,
IS 83 PSIG. INSTRUMENT ACCURACY IS % 2.7 PSIG.
-CORRECTIVE ACTION: REEVALUATE MECHANICAL SYSTEM DESIGN LIMITS AND REVISE SETPOINT, IF REQUIRED.
PROBLEM: i n B. PRESENT SETPOINT FOR STARTING AND LOADING THE ESSEN1IAL AIR COMPRESSORS IS 75 PSIC DECREASING, SYSTEM DESIGN LIMIT IS 73 PSIG. WITH INACCURACIES OF
& 2.7 PSI, SYSTEM DESIGN LIMIT COULD BE VIOLATED.
CORRECTIVE ACTION: REEVALUATE MECHANICAL SYSTEM DESIGN LIMITS AND REVISE SETPOINT, IF REQUIRED.
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L SCR SQNEEB8690 -
' PROBLEM:
A. THE AUTOMATIC CONTROL FOR THE: TURBINE DRIVEN F.W. PUMP s ,IS SET FOR 880 GPM. THE SETPOINT.TO LOCK OUT MANUAL
~ '
. CONTROL IS'880 GPM OR GREATER. THEREFORE, MANUAL
' CONTROL.IS EFFECTIVELY PRESENTED. OPERATING PROCEDURES REQUIRE MANUAL CONTROL.
. CORRECTIVE ACTION: .NCNE. REEVALUATED SYSTEM OPERATION WITH RESPECT TO DESIGN CRITERIA AND DETERMINED THAT A PROBLEM.DID NOT EXIST. 4
- PROBLEM:
B. FS-46-57 HAS A RESET ADJUST WHICH'MUST BE SET TO e MINIMUM TO PREVENT LOCK-UP. SURVEILLANCE INSTRUCTIONS
- DO NOT REQUIRE THIS ADJUSTMENT TO BE MADE.
CORRECTIVE ACTION: NONE. REEVALUATED SYSTEM OPERATION
~
WITH RESPECT TO DESIGN CRITERIA AND DETERMINED THAT A
' PROBLEM DID NOT EXIST.
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