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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
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%_ q TENNESSEE VALLEY AUTHORITY
,, CH ATTANOOGA. TENNESSEE 37401
, 5N 157B Lookout Place
. NOV 061989 .
! U.S. Nuclear Regulatory Commission
( ATTN: Document Control Desk b ' Washington, D.C. 20555 ,
L
[ Gentlemen:
I In the Matter of ) Docket Nos. 50-327
- Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - REPLACEMENT ITEMS PROJECT (RIP) ,
This letter is:being provided.to describe how TVA completed its commitments associated with the.SQN RIP.for the warehouse inventory and seismically sensitive electrical devices, t
c The RIP was organized in November 1986 to address identified deficiencies in i i <
TVA's practices,for the procurement of safety-related replacement items.
Specifically, TVA's procuremer.t program could allow previously qualified
. equipment to be degraded by purchasing replacement components and parts as commercial grade without qualification documentation and without adequate dedication of the items by TVA. While TVA was taking corrective action to t: -
improve the procurement- program, TVA lacked programmatic. requirements for the dedication of commercial-grade >1tems and had not addressed the effect that past procurement practices may have had on the qualification of installed i
- . equipment. As a result, RIP was established to develop and implement a ,
corrective action plan. The primary objectives of RIP were (1) to verify that
.previously quallfled equipment (selsmic and environmental) has not been 1
- degraded through the use of spare parts and replacement items, and (2) to t establish programs and practices that will ensure that prevloesly qualified
~
, equipment (seismic and environmental) will not be degraded in the future through the use of spare and replacement parts.
TVA has completed its. review of the warehouse inventory and seismically ,
sensitive electrical devices. The enclosure provides the status of what TVA has accomplished. Also included is the justification of how TVA applied ,
generic evaluations to a percentage of the safety-related items in the warehouse to be dedicated. SQN's program and processes have not been revised from those previously described to NRC; TVA has only identified a more efficient manner to support dedication of certain groups of items. SQN l i , intends to initiate phased implementation of the generic dedications on November 27, 1989. Based on the activities performed and program requirements in place, TVA considers the commitments to evaluate the warehouse inventory and seismically-sensitive electrical devices complete.
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8911130163 891106 7 DR ADOCK 0500 An Equal Opportunity Employer
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( If you have any questions concerning this submittal, please' telephone i L M. A. Cooper at '615) 843-6651.
L L Very truly yours, f
f TENNESSEE VALLEY AUTHORITY
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Manage 9,Nuclea k.bensingand Regulatory Affairs cc (Enclosure):
[- Ms. S. C. Black, Assistant Director
" for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NH, Suite 2900
Atlanta, Georgia 30323 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road !
Soddy Daisy, Tennessee 37379 j i
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. ENCLOSURE 1 k Page 1 of 4
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SQN Replacement Items Project (RIP) i Program Purpose The primary objectives of the RIP were.(1) to verify that previously quallfted equipment'.(selsmic and environmental) has not been degraded through the use of
- spare parts and replacement items, and (2) to establish programs and practices p that will ensure that previously quallfled equipment (seismic and h environmental) will not be degraded in the future through the use of spare and replacement. parts.
~ Restart Program fu Installed equipment was initially. targeted in activities necessary to support the restart of Unit 2'. The restart scope included an evaluation of 10 CFR 50.49 equipment, seismic evaluation for maintenance of Institute of Electrical and Electronics Engineers (IEEE) 344-1975 qualification within the e Phase I Design Baseline and Verification Program (DBVP) boundary, and n
conditional release controls for items issued to the plant. The m environmentally quallfled equipment program was reviewed and accepted by NRC in Reference 3. To address NRC's questions on seismically sensitive,
. electrically active devices, a detailed evaluation was performed on these
- devices in the warehouse inventory and installed items from those inventory bins. As stated.in Reference 4, the results of the program were reviewed by NRC and found acceptable for the restart of SQN Unit 2. The~ environmentally L ' qualified equipment program and the seismic evaluetion for installed and seismically sensitive, electrically active devices were completed for Unit 2 prior to restart in May 1988.
. Building on the success of the Unit 2 program, TVA demonstrated that SQN Unit I also remained qualified to IEEE 344-1975 and that the installation of ,
commercial-grade items during normal maintenance activities governed by controlled site-specific maintenance procedures did not degrade that qualification. This was accomplished by applying Unit 2 and common equipment
. evaluation to Unit I as defined in Reference 2. Additional Unit i evaluations a were only performed for identified Unit-2 deficiencies.
Postrestart Programs To address selsmically sensitive warehouse items beyond the Phase I j OBVP boundary, TVA performed a seismic screen of the Quality Assurance ;
(QA) II items in accordance with References 1 and 2 and subsequent dedication. This was accomplished by review of procurement reco.ds, equipment
, qualification, maintenance history, industry experience, and recent industry ,
problems. The seismica'ly sensitive items that could not be dedicated were l positively identified by inventory bin location for those located in the l warehouse and by unique aquipment identifier and location for those items that i were installed. Installed equipment will be replaced with qualified material !
'by the end of the Cycle 4 outages in accorlance with previous commitments. '
l Since entering Mode 4 on Unit E in Febr uary 1988, TVA has perfor med an ,
evaluation of intended service application and a detailed engloeeH ng evaluation of commercial-grade items in the warehouse inventory intended for L safety-related applications. The detelled evaluation documented critical ,
x characteristics and verification methods of those characteristics in ,
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. ENCLOSURE 1
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' accordance with plant procedures. As of January 1989, the SQN warehouse ,
pj contained approximately-12,000 items that were considered commercial grade (QAfII) with a potential safety-related application. To date, the review has
- consisted of a detailed technical evaluation of approximately 3,500 of these items. ;
The evaluations revealed that approximately half of the QA II items had been
- misclassified as safety'related and have been downgraded to QA III (nonsafety related). Approximately 15 percent of the QA II items evaluated have been determined to have been procured as nuclear-grade items and have therefore F been revised to reflect a QA I classification. The technical rejection rate of the remaining items for warehouse inventory, excluding seismically -
s sensitive items, is approximately 1.2 percent, of which a large portien is ,
(~ rejections of material that did not have contract traceability or were not economically feasible.to evaluate. Addltional detailed evaluations of QA II
! Items-have been performed for window issue or stock reorder and totai
,g over 1,300_ items to date, ,
Generic Methodology i
Based upon experience gained from completed dedications, TVA determined that generic methodology could be applied to certain warehouse items and would provide:a high degree of confidence that the material could be covered with adequate verification methods for defined critical characteristics. The SQN program and processes have not been revised from that previously described to NRC; TVA has onlyJidentified a more efficient manner in which to support t
, dedications of-certain groups of items. (This' methodology is applied to items already in the warehouse, i.e., not to new procurement items.)
The experience obtained in the completed reviews of the warehouse inventory :
was evaluated'for possible application to the remaining inventory.
Acceptability of a generic evaluation application to inventory items considered as a minimum potential installed applications, technical requirements, technical rejection experience, seismic considerations, and vendor performance. Additionally, industry problems, components, and replacement parts that are the subject of regulatory or industry notifications were reviewed, and associated items were excluded from the scope of the
' generic evaluations. A review of dedication methodologies utilized by RIP on warehouse inventory was performed. The primary acceptance method was based on the< industry consensus guidelines method of special tests and inspections.
Verification methods included augmented receipt inspection and specification of a postinstallation test, but the normal baseline method utilized existing
-receipt inspection, maintenance requirements of like-for-like replacement, and the standard postmaintenance test (PMT) as defined in plant procedures.
The compilation of experience further defined critical characteristics of commodity groups of functionally similar components and the standard verification methods for those critical characteristics. An evaluation was conducted to review inventory line items for inclusion in generic evaluations. This process was developed based on previous procurement l
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ENCLOSURE 1 l- Page 3 of 4'
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[ substation packages, generic evaluation work packages, or contract engineering n 1 group-evaluated material determined to be acceptable. This process for each
~s: stock item provided a' correlation of an evaluation to its applied population and thus gave:a high degree of confidence that an acceptable technical
. evaluation and dedication of inventory line items had been performed. . Iterns L for which generic application.could not be supported will receive specific evaluations in accordance with the established ongoing RIP process. A list of i
the safety-related items for which application of generic evaluation has been determined acceptable is provided in Attachraent 3.
!' , The evaluation summaries were documented for each generic grouping. System classification for functional requirements was defined to provide the basis r .for selection of critical characteristics. Critical-characteristics and verification methods are summarized as well as seismic considerations. -Two p examples of generic evaluations are included in Attachments I and 2.
F Implementation of a generic evaluation to a component or commodity group will L constitute dedication for all items within that group. Documentation _will consist of the generic dedication package of the warehouse inventory and the ,
work request package (including any required PMTs) for item installation. 1 Not.all warehouse items.could be considered appropriate for inclusion to generic evaluation. These items were, however, screened for potential Impact on plant operations, economics, material delivery time, and inventory review experience. These items were placed in a hold status and will not be issued for safety-related application without specific evaluation in accordance with
.the established RIP. process.
Specific Evaluations
.Those items in hold status have administrative procedural controls in place to prevent issue for potential safety-related applications without specific evaluations. . Issuance of inventory for safety-related applications will be l'
performed in accordance with the established RIP process, i.e., warehouse inventory dedication or window issue dedication.
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Controls In order to estab'?sh stronger control on the use of commercial-grade items, r TVA revised the Nuclear Quality Assurance Manual. Nuclear Engineering (NE) '
procedures, and site procedures to control installation and precurement of items intended for safety-related application. TVA has incorporated into its procedures the methodology that is used to evaluate commercial-grade items for use in safety-related applications. This program is consistent with Generic Letter 89-02 guidelines. Additionally, as industry problems are identified, those-problem components will be reviewed to ensure that these items do not degrade the safety-related application.
NE will continue to provide technical specifications for soare and replacement parts through the procurement engineering function to aid in ensuring that safety-related equipment is not degraded by the procurement procen. To enhance the procurement process, TVA deseloped an automated process +o
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[, . , ' i ENCLOSURE 1 p,
Page 4 of 4 ,
8 electronically incorporate procurement specifications into the materials l p management system. To further enhance the program, TVA is developing a corporate standard for the process, and software uploads should begin by the i'
K h end of 1989. .
L Summary- ,
i' .
TVA has completed the evaluation of seismically sensitive, electrically active devices with documentation in place to track replacement of nonquallfled i s installed items by the end of each unit's Cycle 4 refueling outage. TVA has i implemented engineering support to the procurement process as the foundation for this program. ,
Evaluation of the warehouse inventory has been completed on approximately ;
4,800 ltems to date with a very low technical rejection rate. Detailed >
[ evaluation experience has been expanded and applied to certain commodity or ji . functionally similar generic groups where appropriate. This more efficiently utilized the existing RIP process and program to support item dedication. .
i The remaining warehouse commercial-grade inventory (i.e., items in hold b
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status) will be evaluated in accordance with RIP. Additional efforts by TVA in the. area of inventory consolidation and engineering evaluation toward the l' goal.of an engineered operating inventory will further promote efficiency.
This evaluation closes the RIP corrective action at SQN with the exception of seismically sensitive, electrically active device replacement. Acceptability ;
of new procurement items will be ensured through implementation of TVA's .
Upgraded procurement process. NE support of that procurement process serves '
as the long-term action for procurement of spare and replacement parts that
, maintain the design basis of the plant.
References
- 1. TVA letter to NRC dated' April 1, 1987, "Sequoyah Nuclear Plant (SQN) - l Program Plan for Replacement Items Project"
- 2. TVA letter to NRC dated February 10, 1988, "Sequoyah Nuclear Plant'(SQN) -
Replacement' Items Program (RIP) Supplemental Program Plan"
- 3. NUREG-1232, Volume 2, " Safety Evaluation Report on Tennessee Valley ,
Authority: Sequoyah Nuclear Performance Plan," May 1988
- 4. Letter from S. D. Richardson to TVA dated April 13, 1988, " Follow-up Inspection for Piece Parts Procurement (50-327/88-07 and 50-328/88-07)"
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-EXAMPLE Of A CENERIC. DEDICATION EVALUATION '!
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I I , Motor and Parts r Y ,
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[ _c . PLANT FUNCTIONAL' REQUIREMENTS
- _ Motors are used on equipment that is. required to turn, drive, pump, or blow a ,
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multitude of devices or' mediums. Many of these devices are located in im safety-related systems'and perform a safety function. The reliability of 4 l
these motors must be so that they will operate in'a wide.-range of conditions h'
L ' essential to plant. operations or safe shutdown of the plant. !
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' CRITICAL CHARACTERISTICS Part number, ratings (temperature, speed, amps, voltage, power, alternating ,l current / direct current enclosure, flow), function, fit, and seismic
.i . qual 1fication.
p s EVALUATION CLARIFICATIONS AND JUSTIFICATION '
t i Part Number. Rating' J M, Motors'and parts are ordered from ver. dor' catalogs by part number or model if
-number and. technical descriptlon. Ordering the item by a manufacturer's part !
, number ensures-the proper specifications'and ratings apply. In addition, the i n receipt inspection:is performed in accordance with SQN procedures. This !
inspect!on ensures'that the item is the same as specified by the purchasing ~1 contract. ,
. Function'. J l' ,
Functional testing of the motor is confirmed by continuous operation of the !
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' motor during normal operation of.the plant. Instrumentation installed within
,the parameters of the system monitor medium flow rate and pressure or motor
' current and temperature. Instrument readings that are not within the .
acceptable.Ilmits would indicate' potential failure and require investigative l fl: r : action. Safety-related systems require additional PMTs for motors that are ;
i used as, basic' components. Vibration checks after installation are examples of
.these PMT requirements.
O Fit' Trained maintenance personnel and approved plant maintenance procedures ensure ,
the proper fit of the motor. Misalignments and improper fit are also checked ;
and corrected through functional testing. ;
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4 ATTAC4 MENT 1 Page 2 of 4 Seismic Qualification 1 Design practicality and current motor desigin theory establish a high degree of confidence in the size and mass comparability of seismically significant parts. A given motor application will have several output requirements including torque and horsepc.4er. In motor design, these output requirements dictate the sizes of motor windings, armatures, etc., for a highest efficiency combination. Thus, major motor parts and their associated fittings and housings for a given applicat'aon are going to be similar for most manufacturers. The only exceptions to this logic involve more exotic applications and technologies not common to the motor usage in the nuclear power Industry. In addition, most replacement parts are ordered from suppliers of the original equipment manufacturer. This confidence in the similar mass and size of the motors yleids a high assurance that they will not affect the overall seismic qualification of the host.
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SUMMARY
[. , ', GENERIC EVALUATION WP002. .
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'. -81 in' generic evaluation count n~ 7 45'withTissue history'in:last six years
'21 with' detailed evaluations h' '
4: reject)ons .
p& Re.iection Evaluations 4,e The four rejections were for lack of certification for metallic,
- environmentally nonsensitive (i.e., not 10 CFR'50.49) items. -These were:
' conservatively assumed as 50.49 early in the program. 8ased on the environmentally nonsensitive nature of the parts and associated exclusion from 50.49, evaluation'showed that dedication could.be readily performed and thus Lwould not be rejected'at the' current experience level.
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'1 iIndustry/Reaulatory Experience Review a . Inspection and enforcement (IE) notices and-bulletins reviewed for generic appilcability:
a IE Notice 86-03 IE Notice 82-52
.IE Notice 87-08 IE Notice 86-71 IE Notice.86-02
"'- Environmenta'11y: sensitive Limitorque parts.were covered in the RIP.
No other; generic' problems were identified.
Conclusion-The RIP had evaluated environnentally sensitive 50.49 inventory, which is complete.; Detailed evaluation's on metellic piece parts intended for
- safety-related.50.49 applications showed that items were normally purchased 0 - ,
from the equipment manufacturer. Therefore, dedication will be considered complete at. receipt by taking credit for maintenance like-for-like '
o requirements for fit and functional test for functionality and operability.
$>, Reasonable assurance of form is based on normal procurement from the equipment manufacturer and adequate receipt inspection.
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- DOCUMENTATION.
SUMMARY
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' EXAMPLE.OF A GENERIC DEDICATION EVALUATION .c !
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.ITE'M DESCRIPTION 'WP087 C '
- Containment' Air Lock. Door Parts '
l ff- . FUNCT'!ONAL REQUIREMENTS ,
- ? Proper functioning of these. doors is necessary to maintain the integrity of i 3 f- .the' reactor building primary containment pressure boundary. l
..., ; CRITICAL. CHARACTERISTICS ,
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Dimensions, material,'part number, function, and seismic. ;
o 0,s EVALUATION; CLARIFICATIONS AND JUSTIFICATION v
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, : Material.. Function. and Part Number This. information-l's specified in design. basis documents and confirmed at the.
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. time of receipt for these items in accordance with standard SQN procedures, c
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' Dimensions and Function p Newly ~ mounted doors and repaired doors are required to be-inspected in M i L'accordancewithSQNmaintenanceproceduresensuringaproperfitand: adequate h : function. Pressure-retaining adequacy.and overall operability are tested
- every 31 days in~accordance with standard SQN procedures.
L U : Seismic .
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Door parts.are small and are affixed to the door in stable configurations so
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thatethe' seismic integrity of the door is not compromised as a result of its
.. replacement or: repair. Seismic loading was.also included as a part of the design. basis for.the doors.
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- DOCUMENTATION.
SUMMARY
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GENERIC EVALUATION WP087
'CONTAINHENT" AIR LOCK 000R, PARTS r
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l problems' were identified for: Chicago Bridge & Iron components. -
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' 3 i NoLadverse problem,s'were'ident1 fled that would impact this generic evaluation.
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SUMMARY
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GENERIC EVALVATION HP087 1 1
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' SAFETY-RELATED GENERIC EVALUATIONS '.,
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. Evaluation Number Title 1 m ;
., WP001 Valve Operator and Actuator Parts [
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WP002 Motors.and Parts'. '
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- HP005 ' Olesel: Generator Parts d h M ,q'l . [
. WP006' Bulk Electrical _ Commodities i WP015 Filters (hlgh-efficiency particulate air). .
? WP016 - Door Parts (Auxiliary Building Secondary. t A Containment Enclosure and Fire)' '
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, WP021 ' Instrumentation and Parts i WPO40 ,
Couplings- ;
WP052 Grout '
t M, . H .WP054- Bushings, Rings, and Spacers h', WP055 Auxiliary Feedwater Pump Parts ,e i WP060 Valve'Positioners, Controllers, and Parts b Op . , WP063~ , Radiation Monttoring Equipment-i- ; 'WP074 Snubbers and Snubber Parts !
L 'WP080 . Compressors
.WP082 Printed Circuits Boards -
WP087: Contalnment Air Lock Door Parts j r '
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