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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
- -.
- - ~ .~ - . . . . - - - - - . . - - . -. - - . - . ~ ~ .
e TENNESSEE VALLEY AUTHORITY CH ATT ANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II e ")/ / , $p %
May 5, 1981 S N
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t MAY 111991. [
Director of Nuclear Reactor Regulation va, % , % , '
V " '58""
Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 / P Division of Licensing U.S. Nuclear Regulatory Commission
<v gN Washington, DC 20555
Dear Mr. Schwencer:
In the Matter of ) Docket No. 50-327 Tennessee Valley Authority )
In the TVA/NRC meeting of April 1, 1981, NRC requested that TVA submit a seismic margin program plan and a list of components to be investigated.
Enclosed is TVA's program plan for the seismic design margin review of the Sequoyah Nuclear Plant as required by item 2.C(6) of the full power operating license for unit 1.
In September 1981, TVA will get in touch with NRC to discuss the advis-ability of a TVA/NRC meeting concerning interim progress. The TVA program '
is expected to be completed and results available for presentation by January 2, 1982.
Very truly yours, TENNESSEE VALLEY AUTHORITY f
M. Mills, Manager Nuclear Regulation and Safety Sworn tgand subscribed before me thisd- day ofh444 1981 0
- Notary Public My Commission Expires '5"/$
Enclosure OD I s
/
f 81051203l3 " " ' - ' == ""* c - "' I 1
. . ENCLOSURE
. SEISMIC DESIGN MARGIN REVIEW PROGRAM _
SEQUOYAH NUCLEAR PLANT .' a.,
Introduction The TVA seismic evaluation program was presented to the Nuclear Regulatory Commission (NRC) in March 1979. Because of time limitations, NRC was not able to complete its review of all equipment; only mechanical equipment critical to safe shutdown was reviewed and documented. The werk completed and the scope of work to be done are discussed for each of the four items of seismic qualification. Items 1 and 2 were completed in 1979, and no further work is anticipated en these items. The TVA program concentrates on item 4, safety-related equipment.
The format of the March 1979 presentation was extremely effective in communicating basic technical information for both NRC and TVA. This presentation consisted of the exchange of technical data, criteria, and engineering rationale directly across the table between TVA and NRC cognizant engineering employees. Copies of technical information such as pertinent criteria, qualification report excerpts, engineering notes, etc.,
were provided to the NRC representative upon request as the presentation proceeded.
TVA proposes that this same informal technical information exchange format be used for a followup presentation. For obvious reasons, the presenta-tion would be most effective if conducted in the TVA offices in Knoxville.
TVA Program
- 1. Category I structures - Category I structures have been shown ~
acceptable for seismic loading associated with the 84th perce.ntile site-specific response spectra. This includes the original analyses of Sequoyah Nuclear Plant (SQN) soil-supported structures which reflect a degree of conservatism sufficient to envelope the higher seismic levels associated with the 84th percentile earthquake. No further effort is required. ,
- 2. Safety-related piping systems - The reanalysis of selected systems effectively represented a reevaluation of all safety-related piping systems. From a review of all . safety-related piping systems, those systems with the highest ratio of stress resulting from combined leads to the corresponding allowable stress were selected for reanalysis to the 84th percentile earthquake. With these most critical systems having been found acceptable, it is reasonable to conclude that the remaining systems are at least equally acceptable.
The reevaluation of the piping systems and the conclusion that they are acceptable against the 84th percentile earthquake applies equally to all interfaces of the piping systems with safety-related equipment.
The piping reevaluation included confirmation that the original criteria for the seismic qualification of the pipe-supported equipment (valves, strainers, etc.) was not exceeded by the 84th fercentile earthquake. It was further confirmed that the original criteria for piping systems nozzle loads imposed on floor-mounted equipment such as pumps was not exceeded..-
3 HVAC ducting - Because of time limitations, TVA was able to only briefly touch on the consideration of HVAC cucting reevaluation during the March 1979 presentation. The criteria which dictates the
. ~ . . . . . . - . . - -
' installation and . support of the HVAC ducting reflects a degree of I conservatism which is more than sufficient to envelope the increased - T seismic levels of the 84th ' percentile earthquake. A more detailed " - ' '
l discussion to HVAC ducting and duct-mounted equipment will be included, i
in the remaining work for the followup program.
- 4. Safety-related equipment - The March 1979 evaluation and report to j .NRC addressed only selected items of mechanical equipment critical to
- safe shutdown. In the followup program, TVA will continue and expand the presentation of equipment evaluation for 84th percentile earthquake as follows.
- a. Consistent with the original guidelines developed with NRC regarding the scope of this reevaluation effort, the items of equipment to be considered will be limited to TVA-procured, balance-of-plant equipment. It is understood that the NSSS- i supplied equipment has been evaluated by NRC with the NSSS vendors I on a generic basis.
- b. After review of mechanical equipment listing, TVA will include any critical items which were not covered in the March 1979 '
presentation.
- c. TVA will provide a thorough presentation of critical Category I instrumentation and electrical equipment qualification to show that ,
it envelopes the 84th percentile earthquake. -
The completion of the TVA program of evaluation of critical items of equipment will provide a sufficient basis to form the engineering conclusien that the seismic qualification of all'elec-
.' trical and mechanical equipment critical to safe shutdown can be
~
shown to be sufficiently conservative to envelope the P4th
Note: Tabulations of safety-related mechanical and electrical
, equipment to be considered in the reevaluation effort are included in the attached TVA correspondence. ~
Program Schedule TVA has committed to complete the equipment reevaluation program by
- Harch 1, 1982, as reflected in SQN's operating license. To support this schedule,- the following milestones have been established.
- 1. Interim status - In September 1981, TVA will get in touch with NRC representatives en an informal basis to discuss the progress of the reevaluation and any problems which uight have been encountered. The advisability of a TVA/NRC interim meuting will be discussed and scheduled if considered appropriate.
- 2. Presentation of results - January 2, 1982, has been established as the target date for completing the reevaluation effort. By this date, TVA will get in touch with NRC representatives to coordinate a meeting for the presentation of equipaient reevaluation results. A meeting held as i soon as possible af ter this date would leave time to resolve any '
r questions or concerns rega'rding the presentation of reports.
l 3 The effort will be completed by March 1, 1982.
l E- --
un a t.u. n ARS GOVERN 31ENT ATTACI: MENT A1 *
~bemOYd15dum TENNESSEE VALLEY AUTHORITY '
'CEB '800826 4007' -
TO : Those listed FRO)! : R. O. Barnett, Chief,' Civil Engineering 3 ranch, W9D224 C-K DATE :
AUG2 61980
SUBJECT:
SEQUOYAH NUCLEAR PLANT - SEISMIC REEVALUATION OF SAFETY ,RELATED EQUIPMENT
~
Reference:
Supplement No. 2 to the Safety Evalua' tion Report, NUREC-00ll, dated August :,, 1980.
As outlined in the reference TVA has co=mitted to reevaluate the seismic qualification of safety-related electrical and mechanical equipment against the more severe 84th percentile earthquake. This effort will inclu'de all equipment necessary for decay heat removal. Civil Engineering
. Branch's (CEB's) Component Qualification Section will be oponsible for' the technical reevaluation; however, your assistance'will be required to accomplish,this task in a timely manner. '"
~
The ~ pacing ites for this effort is, of course, the definition of specific ,
iten.s of electrical and mechanical equipment critical to the decay heat r_epoval process. It is requested that the Nuclear Engineering Branc,h_ (NE3)
/vith necessary support from the Electrical Engineering Branch (EEB1/
provide this detailed list of equipment. In order to provide a timely response to the Nuclear Regulatory Commission (h*RC), the requested ...
equipment lists should be provided to CEB's Component Qualification Section by October 15, 1980. If, for any reason this target date cannot be net, advise CEB as to your proposed alternative completion date. ,
A large portion -of this task will be that of retrieving the seismic qualification documentation for each iten of equipment from procurement contract files. It is requested that the Mechanical Engineering Branch (MEB) and EEB each designate an individual to coordinate the qualifica-tion report retrieval effort among the various procurement organizations.
Any comments or questions concerning the above should be directed to F. H. Coleman at extension 2157. .
R. O. Barnett F. W. Chandler, W3Cl26 C-K C. A. Chandley, W10D224 C-K G. F. Dilworth, W10Cl26 C-K E4B37 C-K '
k ba R. W. Cantrell, 204 GS-K (2)
- ~
\
! Buy U.S. Savings Bonds Regularly on tie Payroll Savings Plan
f.i M3 %01126 252 ATTACHMENT A2 .
- R. O. Barnett, Chief, Civil Engineering B anch, W9D224 C-K 4 % -
John A. Raulston, Chief Nuclear Engineer, W10C126 C-K , x El_
N 881S8 -
801204E0039 SEQUOYAH NUCLEAR PLANT - SEISMIC REEVALUATION OF SAFEIT-RELATED EQUIPMENT
- i
.ll 1l 1
Reference:
Tour memorandus to Those listed dated August 26,1980 (CEB !
800826 007) - -
Your me=crandus requested a listing of electrical and mechanical
. equipment critical to the decay heat removal process as input to the g seis=ic qualification reevaluation program for SCN. The attachment presents a table of safety-related =echanical equipment to be used in M- ,
defining the extent and detail of the program. Thi's listing includes d 'l
- only major mechanical equipment and does~not include NSSS equipment, .
other than a systems list, according to your guidance. Also, it f should be noted that the listing does not individually specify certain c1=ponents (e.g. , valves and da=pers) within an identified system.
g.
p v
We are requesting by this memorandum that EL supply a corresponding listing of major electrical equipment necessary to support the N -
identified mechanical equipment.
More detailed and specific mechanical and electrical equipment 1ists -
g can be generated, if required.
N -
4
~s M "N.'
&h John A. Raulston -
yp RSM:PJB Attachment .
f
~~ ' ce "( Attachment): .
(M R. W. Cantrell, 204 GB-K (2)
F. W. Chandler, W8C126 C-K - Please provide the electrical
{
. equipment list as discussed above. ;
C. - A. Chandley, W10D224 C-K ,
R. A. Costner, Wild 190 C-K r.
g DS, E4B37 C-K
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MBsMME M EMMMiBEf8 mms -
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Drawinc.
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Auxiliary Power 5.9 kV/480V Press" Htr Transformers l A-A 45N234 1B-B 45H234
" 45H234
. 2A-A 28-8 45H234 480V Distribution Panel "
Bds for Press Htr lA-A 18-B ,
2A-A 28-B 120V AC Vital Control Static Inverter 1-I,1-II,1-III,1-IV 45N230 Power 2-I, 2-II, 2-III, 2-IV 45N230 Instr. Pwr Bds. 1-I, 1-II, 1-III, 1-IV 45N230 2-I, 2-II, 2-III, 2-IV 45N230 125V DC Vital Control Battery Chargers I & II, spare 1 45H230 Power III & IV, spare 2 45N230 Transfer Devices for Batt Charcers I & II, 45N230 (2) spare 1 Transfer Devices for Batt Chargers III & IV 45H230 (2) spare 2 Vital "
Batteries I & II 45N230 III & IV 45N23.0 Vital Batt Bd. I & II 45N230 III & IV 45N230 Electrical High Voltage Power Penetrations Penetrations Nuclear Instr. System Penetrations
. Control Rod Pos. Ind Penetrations low Voltage, Power Control, and Indication
. Penetrations
- Thermocouple Penetrations , ,
e 9
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=,
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! P00R~0RIGINAl.
i l
System Component
. ix 0rawine-Auxiliary Power 6.9 kV Shutdown Board Logic Panels 456S7005 ,
6.9 kV Swgr for New DG .
45N728 6.9 kV Air Interrupter Switch for DG 6.9 kV Shutdown Board 1A '
45N724-1 6.9 kV Shutdown Board 1B ._____.
45N724-1 M 6.9 kV Shutdown Board 2A 45N724-2 6.9 kV Shutdown Board 2B 45N724-2 480V Shutdown Board 1Al-A r. 2Al-A . . 45N749-1 %
1A2-A &. 2A2-A ~45N749-2 C.C3 181-B & 281-3 45N749-3. %
480V Rea:. tor Mov Bd 1 Al-A 182-8 & 2B2-B 45N749-4 45N354-Wl 181-B - 45N366
-Ql 1A2-A 45N364 gl 182-8 45N366 2Al-A 45N368 D 2B1-B 45N370 Q 2A2-A 45N36B CL., l 282-8 45N370 g 480V Reactor Vent Board 1 A-A 45N380 18-B 45N380 2A-A 45N382 28-B -
45N382 480V Control & Auxiliary Gidg Vent Bd 1Al-A 45N383 1B1-B 45N384 1A2'-A 45N333 ;
182-B 45N384
" I 2Al-A '
45N385
"- 281-B 45N386
" g 2A2-A 45N385 '
2B2-B 45N3SS i 480V Diesel Auxiliary Board 1Al-A .
15N216' '
1A2-A 15N216 i 181-B 15H216 3
, 132-B 15N216 2Al-A 15N218 l 2A2-A 15N218 281-B 15N218 l 2B2-B 15N218
. 6.9kV/480V Shutdown Board Transfomerr,1 Al-A 45N332
" l 1A-A 45N332 "E
1A2-A 45N332 1 181-B 45N33E IB-B 45N332 -
, ., 182-B 4bN332 2Al-A 45N332 2A-A 45N332 I 2A2-A 4EN332 '
281-B 45N332 !
2B-B 45N332 ;
. 2B2-8 45N332
'. l l l
SEQUOYAH NUCLEAR PLANT
.u '
Mechanical Safety-Related Equipment List , ;
System . Component . Drawing
47W801-1 Relief Valves 47W801-1 : .
. *SG 3~owdown Isolation Valves 47W801-2 ,,-
47W803-1 .
Motor-Driven Pu=ps 47W803-2 Valves 47W803-2
- Chemical Volume and Control NSSS Supplied
- Safety Injection NSSS Supplied (Except Storage Tank 47W811-1)
- Upper Head Injection NSSS Supplied
Heat Exchangers 47W812-1
Protection Pwsps 47W832-1 Valves 47W832-1
. Strainers -
47W832-1,
.
- Ice Condenser Dcors and Passive Portion of ,.,
System which is Required for LOCA 47W814-2 Control Rod Drive NSSS Supplied
- Diesels Generator D-G Manual Engine D-G Manual D-G Msnual C@lers ,
Water (See note 6,) Pumps 47W845-1 & 5 Valves 47W845-1 to 5 Traveling Water Screens 47W845-1 & 5 Screen Wash 47W845-1 & 5 Strainers 47W845-1
- Control Air Auxiliary Air Compressors 47W848-1 i
After Coolers 47W848-1 Air Receivers -
47W848-1 Air Dryers 47W848-1 Filters 47W848-1 Valves 47W848-1
. Tanks 47W839-1 l Filters 47W839-1 Valves 47W839-1
, Towers & Fans 47W845-1 Traveling Screens & Screen Wash 47W845-1 Valves 47W845-1
_ P00R 0RIGlNAl
. , l System Component iDradini
- Standby Diesel Oil 7-Day Tanks 47W8401 1 Day Tanks 47W840-1 Motor-driven Pumps .. 47W840-1 Engine-driven Pumps
. Filters 47W840-1 Valves 47W840-1
- Spent Fuel Pool Cooling NSSS Supplied
===J
===== -
Thermal Barrier Booster Pu=ps 47W859-2 M
- Main Control Room A/C See Note 1 47W865-3 480-V Bd. Room 4/C See Note 1 47W865-6 g *Elec.* Bd. Room A/C See Note 1 47W865-7
- Shutdown Bd. Room A/C See Note 1 '
47W866-8 and Ventilation 47W866-3 O Air Return System
- 480-V Transformer Rm Ventilation Exhaust Fans 47W866-3 Intakes ~
47W866-3 Dampers 47W866
- Vital Battery Rm Exhaust Fans ,
47W866-3 Ventilati.,a Dampers 47W866-3 Emergency Gas Treatment System Fans 47W866-1
, Filters 47W866-1 Heaters 47W866-1
. Demister 47W866-1 Aux Bldg Gas Treatment System . Fans 47W866-10 Filters Heaters Dampers Vacuum Relief Demister
- T'urbine-driven Aux. Feed
- Control Bldg. Ventilation (Pressurization, Emerg, i
Pressurization, Air l Cleanup, Battery
! Exhaust) . Facs 47W866-4 l . Dacpers 47W866-4 i .' Fil'ters .47W866-4 Fire Dampers 47W866-4 l NSSS Supplied l Waste Disposal System t
l 204003/5
. . - - . ~ .
l System Component Drawing' l
- Safety Feature Equipment .
Coolers (Serves RHR, -
SIS, CCS, EGTS, Boric .
Acid Transfer, CS,S, '
AFW, SFPCS, and Centrifugal Charging Pumps and Pipe Chases and Penetration Rooms) Air Handling Units 47W845-4
- Flood Mode Boration and Makeup (See Note 2) Pumps 47W809-7
. Tank 47W809-7 Valves 47W809-7 Containment Vaccu:a -
Relief
- Valves 47W866-1 Miscellaneous Cat.'I cran's#
Fuel Transfer Tube Fuel Transfer Conveyor New and Spent Fuel Racks -
. Pressure Confining Doors
Watertight Doors and Seals ,
RER Sump Manways and Seals ERCW Personnel Access Doors and Scals
, Containment Personnel Access Doors and Seals Missile Barriers for A/C Enclosures
, Aux. Bldg. RR Access Hatches and Seals Containment Equipment Access Hatch and Seal Escape Hatches and Seals Shield Door and Enclosure
- Seal Between Ice Condenser and Containment Vessel Railroad Access Doors Spent Fuel Pit Bridge Crane Manipulator Crane
- CCW Discharge Gates and Roists Note 1: The total system should be included; i.e., AH1's, chillers, valves, fans, dampers, filters, pumps, compressors, condensers, etc.
Note 2: Only a limited seismic requirement is applicable to this system.
Note 3: The listing does not include containment isolation valves in l nonsafety-related systems. These valves are also safety-related.
l Note 4: This list does not include monitoring equipment for radiation and neutron flux, nor does it include the reactor protection system.
P0OR ORIGINAL
Note 5: The CO 2 and lube oil ventilation, fuel oil transfer roco exhaunt '
corridor and toilet room ventilation, and unit heaters 'dodco! ' ,
perform a primary safety function. -
Note 6: This includes the ERCW pumps, valves, strainers, and traveling water screens at the intake pumping station, as well asthe ERCW intake station, until the barge impact concern for the ERCW intake station is resolved. This equipment at the~ intake pu= ping station may be necessary if there is barge impact of the ERCW intake station.
However, barge impact need not be considered situltaneous with a
--- J seismic event. .
==*: . .
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CD M
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I
- Needed for decay beat removal only in event of fire-caused loss of the cables for ERCW intake prior to completion of ECN L5298.
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.I'
, . ATTACH' MENT A3 e 4
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UNITI:D STATES CnVERNMENT ,
.TesEsseM49.!sMacfnE;rdri-Memorandum ,
R. O. Barnett, Chief Civil Engineering Branch, W90224 C-K T'S ' J. A. Raulsta i, Chief Huclear Engineer, W10C126 C-X rniin : F. W. Chandler, Chief. Electrical Engineering Branch, W3C126 C-X DATE : February 26, 1981 ,,
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81*H M T: SEQUOYAH NUCLEAR PLA'iT SEISMIC REEVALUATION OF SAFETY-RELATED EQUIPMEtiT Refer to J. A. Raulston's memorandum to R. O. Barnett dated November 26, 1980 (NEB 801126 252), concerning Balance of Plant (BOP) equipment to undergo seismic reevaluation as a result of Safety Evaluation Report (SER) requirement. ,
The referenced tremorandum requested the Electrical Engineering Branch i to supply a listing of major electrical equipment necessary to support the mechanical equipment identified in the reference. The major BOP '
electrical equipment is shown on the attached list. Not listed are motors since they are considered part of the driven equipment for seismic evaluation purposes'and are assumed to be Itsted with the driven -
equipment. _
All BOP safaty related instruments are included fri one of the "
three following categories: '
- 1. Main Control Panel Mounted
- 2. Local Panel (racQ Hounted
- 3. In-line Mounted Per discussions between CEB's F. H. Coleman and our B. O. Buchanan, no further detailed listing is necessary for the instru.tentation.
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