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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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TENNESSEE VALLEY AUTHORITY Watts Bar Nuclear Plant P. O. Box 800 Spring City. Tennessee 37381 February 9, 1987 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Harold Denton, Director of Nuclear Reactor Regulation In the Matter of the Application of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 EMPLOYEE CONCERNS TASK GROUP (ECTG)
In accordance with the NRC's request, a list of concerns which are related to each issue noted in the Sequoyah NRC SECY Plan is hereby submitted for your information (Enclosure 1). Also included in this list are the element reports applicable to each concern. Enclosure 1 is divided into 15 sections corresponding to each of the NRC SECY Plan issues with the exception of
" Wrongdoing, Intimidation, and Harassment." The list of concerns for this issue has been identified in the investigation efforts by the Office of the Inspector General.
This list was complied by performing a keyword data base search through the text of the employee concerns. Keywords relative to the NRC SECY Plan issue were utilized and are listed on Enclosure 1 at the beginning of each section. This method is subjective in nature. However, when draft Safety Evaluation Reports (SER's) are received from the NRC, the appropriate ECTG groups will review them to verify that there is no conflict between the SERs and the element reports, and we will reassess the list of concerns to identify additions or deletions at that time. Information derived from the SER reviews will be provided to Sequoyah licensing.
If you have any questions, please contact Martha Martin at (615) 365-3587.
Very truly yours, TENNESSEE VALLEY AUTHORITY h he r 2< e h
[n/J.Watts A. Mcdonald Bar Nuclear Plant Site Licensing Manager cc (See page 2.):
8702110154 870209 0 DR ADOCK 05000327 'h PDR An Equal Opportunity Employer
2 U.S. Nuclear Regulatory Commission cc (Enclosures):
Mr. James M. Taylor, Director ,
Office of Inspection and Enforcement '
U.S. Nuclear Regulatory Commission Washington, D. C. 20555 U.S. Nuclear Regulatory Commission ,
Region II '
Attn: Mr. Gary Zech 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Nr. B. J. Youngblood, Project Director PWR Project Directorate #4 Division of PWR Licensing - A U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Room 440, 5 Story Phillips Bethesda, Naryland 20814 Nr. Richard H. Wessman U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 3601T l
l l
/
I 9
Enclosure 1 1
i
r I. Categnry - Emplevta Concarns Listing of all employee concerns was provided to the NRC on 9/3/86.
II. Category - Allegations Listing of all allegations was provided to the NRC on 11/26/86.
III. Category - Equipment Qualification Key Words: 10 CFR 50.49 Electrical Equipment Environmental Environmental Qual.
EQ EQP IEEE-323-1974 Maintenance NUREG 0588 Raychem Splice Westec 3436T
III. Category - Equipment Qu711ficatirn (continued)
Concerns: HI-85-077-N13 EN21002 WBN-223 MC40400 IIS-85-068-002 EN21001 MC40700 IN-85-129-003 MP70601 WBN-245 OP31309 OP30801 WBP-85-017-005 OP30706 IN-85-336-003 MC40200 WBP-85-018-OO2 MP70605
, IN-85-518-OO2 MP71700 WI-85-100-OO3 OP30102 IN-85-601-001 OP30705 WI-85-100-005 EN21002 IN-85-601-002 MP70601 WI-85-100-034 EN20302 OP30801 EN20303 OP30709 IN-85-962-003 C011200 WI-85-100-040 MC40400 IN-85-993-008 QA80405 XX-85-070-005 OP30704 IN-86-259-X11 EN20104 XX-85-094-008 MC40400 EN21304 XX-85-094-013 EN21002 IN-86-316-002 OP30803 XX-85-122-004 OP30202 IN-86-316-005 OP30801 XX-85-122-OO5 OP30202 IN-86-316-XO9 OP30802 XX-85-122-008 OP30102 MAS-85-002 OP30201 XX-85-122-OO9 OP30102 MAS-86-004 OP30202 XX-85-122-010 OP30102 MRS-85-005 OP30201 XX-85-122-014 EN21002 OE-QMS-1 QA80104 XX-85-122-015 EN21002 OE-QMS-4 EN21002 XX-85-122--016 EN21002 OW-85-OO7-010 C010500 XX-85-122-045 MC40400 SQM-86-009-001 QA80203 XX-85-122-046 MC40400 SQP-86-009-004 OP30801 XX-85-122-047 NC40400 SQP-86-OO9-XO3 QA80202 XX-85-125-006 QA80202 TAK-85-001 OP30201 IV. Category - Welding Key Words: ASME AWS Certifications Criteria Defect Falsified Filler ISI NDE Nondestructive PSI Qualification Repair Rework Rod Weld
IV. Category - Welding (centinued)
Concerns: 285-0162-005 WP-25-SQN IN-85-441-003 WP-01-SQN BEM-85-001-001 WP-16-SQN IN-85-451-001 WP-08-SQN BEft-85-001-002 WP-16-SQN IN-85-453-009 WP-01-SQN BFft-85-001-001 WP-16-SQN IN-85-454-004 WP-01-SQN BFM-85-001-002 WP-16-SQN IN-85-458-001 WP-02-SQN DHT-85-001 WP-21-SQN IN-85-476-004 WP-06-SQN EX-85-OO8-001 WP-07-SQN IN-85-480-004 WP-03-SQN EX-85-021-001 WP-01-SQN IN-85-493-004 WP-03-SQN EX-85-021-002 WP-03-SQN IN-85-501-001 WP-19-SQN EX-85-039-001 WP-01-SQN IN-85-503-001 WP-19-SQN EX-85-039-003 WP-15-SQN IN-85-532-004 MP 70605 EX-85-042-003 WP-03-SQN IN-85-532-005 WP-03-SQN EX-85-059-001 WP-08-SQN IN-85-532-006 WP-19-SQN EX-85-061-004 EN 20404 IN-85-540-OO1 WP-19-SQN HI-85-050-002 QA-80307 IN-85-543-002 WP-19-SQN IN-85-007-001 WP-04-SQN IN-85-556-001 MP 70101 IN-85-007-OO3 WP-17-SQN IN-85-589-002 OP 30806 1
IN-85-021-OO3 WP-19-SQN IN-85-600-001 WP-12-SQN IN-85-021-X05 WP-19-SQN IN-85-612-006 WP-19-SQN IN-85-109-002 EN 22205 IN-85-612-XO7 WP-19-SQN IN-85-109-003 EN 22206 IN-85-613-001 WP-15-SQN IN-85-109-003 EN 22206 IN-85-627-036 WP-03-SQN IN-85-113-003 WP-03-SQN IN-85-657-001 WP-17-SQN IN-85-127-001 WP-17-SQN IN-85-672-003 WP-01-SQN IN-85-134-002 WP-04-SQN IN-85-706-001 WP-07-SQN IN-85-167-XO6 WP-19-SQN IN-85-725-X14 WP-19-SQN IN-85-192-002 WP-08-SQN IN-85-725-X15 WP-19-SQN IN-85-212-001 WP-16-SQN IN-85-767-003 WP-02-SQN IN-85-234-001 WP-01-SQN IN-85-770-002 WP-03-SQN IN-85-247-001 WP-12-SQN IN-85-770-003 WP-19-SQN IF85-247-002 WP-13-SQN IN-85-770-XO7 WP-19-SQN IN-85-271-001 WP-11-SQN IN-85-778-001 WP-03-SQN IN-85-273-001 WP-08-SQN IN-85-778-XO7 WP-19-SQN IN-85-282-002 WP-11-SQN IN-85-815-001 WP-03-SQN IN-85-297-003 EN 21509 IN-85-835-002 WP-03-SQN IN-85-299-003 WP-19-SQN IN-85-940-XO4 WP-03-SQN IN-85-303-001 WP-13-SQN IN-85-965-OO1 WP-19-SQN IN-85-335-002 WP-19-SQN IN-85-981-001 WP-06-SQN IN-85-337-002 WP-01-SQN IN-86-019-001 WP-02-SQN IN-85-339-005 WP-OS-SQN IN-86-047-OO1 WP-14-SQN IN-85-346-003 WP-03-SQN IN-86-140-002 CO 11300 IN-85-352-OO1 WP-03-SQN IN-86-143-002 WP-19-SQN IN-85-352-002 WP-01-SQN IN-86-150-OO1 WP-01-SQN IN-85-372-001 QA 80203 IN-86-158-006 WP-14-SQN IN-85-405-001 WP-15-SQN IN-86-167-001 WP-01-SQN IN-85-406-002 WP-09-SQN IN-86-167-005 WP-19-SQN IN-85-406-003 WP-04-SQN JAN-85-OO1 QA 80201 IN-85-411-002 WP-12-SQN JLH-85-OO1 QA 80303 IN-85-424-OO1 WP-01-SQN JLH-85-002 WP-24-SQN IN-85-424-OO4 WP-01-SQN JLH-85-003 WP-22-SQN IN-85-424-006 WP-01-SQN JLH-85-005 QA 80201 IN-85-424-007 WP-01-SQN NS-85-OO1-001 WP-02-SQN IN-85-424-011 WP-03-SQN OE-QMS-8 CO 11301 IN-85-424-X13 WP-19-SQN OW-85-003-OO1 EN 22202
! IN-85-426-001 WP-01-SQN PH-85-012-XO3 WP-05-SQN IN-85-426-002 WP-03-SQN PH-85-035-002 MC 40300 i
r IV Category - Welding (Continued)
PH-85-040-001 WP-02-SQN
.PH-85-052-OO2 WP-03-SQN PH-85-052-XO3 WP-03-SQN SQM-85-001-001 WP-16-SQN SQft-8 5-001-002 WP-16-SQN SQM-86-005-OO1 I-86-115-SQN SQM-86-005-XO2 I-85-115-SQN SQM-86-OO8-001 WP-20-SQM SQN-86-002-002 EN 21202 W8M-85-OO1-001 WP-16-SQN WBM-05-001-002 WP-16-SQN WBP-86-007-001 WP-15-SQN WI-85-003-001 WP-19-SQN WI-85-003-XO2 WP-19-SQN
.WI-85-013-003 WP-02-SQN WI-85-030-OO7 WP-16-SQN WI-85-030-008 WP-19-SQN WI-85-030-010 WP-10-SQN WI-85-041-001 WP-01-SQN WI-85-041-OO2 WP-06-SQN WI-85-041-006 WP-02-SQN WI-85-041-008 WP-02-SQN WI-85-053-004 WP-01-SQN WI-85-055-OO1 WP-19-SQN WI-85-056-OO1 WP-19-SQN WI-85-081-007 WP-06-SQN WI-85-084-001 WP-19-SQN XX-85-013-001 XX-85-013-001 XX-85-041-001 I-85-756-SQN XX-85-045-OO1 WP-07-SQN XX-85-049-001 I-85-135-SQN XX-85-049-XO3 I-85-135-SQN XX-85-054-001 I-85-346-SQN XX-85-065-001 I-85-750-SQN XX-85-068-OO6 WP-01-SQN XX-85-068-007 I-85-636-SQN XX-85-069-OO1 I-85-373-NPS XX-85-069-003 I-85-738-SQN XX-85-069-007 I-85-373-NPS XX-85-069-X13 I-85-373-NPS XX-85-083-001 I-85-652-SQN XX-85-086-OO3 I-85-560-SQN XX-85-088-003 XX-85-088-OO3 XX-85-098-001 WP-18-SQN XX-85-100-001 XX-85-100-001 XX-85-101-006 XX-85-101-006 XX-85-102-011 I-85-735-SQN XX-85-108-OO1 I-85-776-SQN XX-85-108-OO2 I-85-776-SQN XX-85-124-001 WP-23-SQN
_ . _ _ __ a
~
V. Cateocry - D7 sign Control Mey Words: Alternate Analysis
~
Configuration Modification Alteration Criteria Repair Anchor Design Review As-Built DNE Rework As-Configured Drawing Small Bore Piping As-Designed ECN Structural Change FCR USQD Concerns: BFNIESC-85-03 OP30713 IN-86-209-003 EN20405
.QA80000 IN-86-261-002 C011200 BNPQCP10.35-1 EN23106 OE-QMS-3 EN20801 EX-85-181-001 MC40201 OE-QMS-8 C010400 MC40301 EN22203 NC40503 OW-85-003-001 EN22202 HI-85-094-N02 EN20601 PH-85-038-OO1 EN20406 I-85-128-NPS EN20106 SQN-86-001-001 EN21804 EN20411 SQN-86-OO1-OO3 EN21801 EN20501 SQN-86-002-001 EN21804 EN20502 SQN-86-OO2-002 EN21202 EN20601 SQN-86-002-003 EN21801 QA80303 WBP-86-025-X02 EN20405 I-8 5-993-NPS EN23105 WI-85-091-015 EN20403 IN-85-010-004 EN23101 EN22007 IN-85-024-001 EN22001 WI-85-100-011 EN23803 IN-85-029-002 EN20401 WI-85-100-018 EN21302 IN-85-031-001 C010400 WI-85-100-019 EN20103 IN-85-038-001 EN21801 EN20104 IN-85-039-001 EN21801 EN21303 IN-85-039-002 EN21801 WI-85-100-037 EN20106 IN-85-039-003 EN21807 WI-85-100-038 EN20104 IN-85-103-OO1 C011301SQN EN20404 IN-85-103-003 EN22012 WI-85-100-041 EN20105 IN-85-103-N04 EN20405 EN20406 IN-85-109-OO2 EN22205 EN20406 IN-85-109-XO4 C011301SQN WI-85-100-043 EN20501 IN-85-110-004 EN20503 EN20502 EN21201 EN20503 IN-85-148-001 EN20405 EN20106 IN-85-152-001 EN20601 WI-85-100-044 EN20103 IN-85-218-001 0017300 WI-85-100-045 EN20601 IN-85-305-NO3 OP30704 WI-85-100-046 EN20405 IN-85-436-006 QA80501 WI-85-100-047 EN20405 IN-85-545-XO6 EN23208 WI-85-100-055 EN20406 IN-85-886-001 EN2OlO3 XX-85-062-001 QA80503 EN20404 QA80511 EN22003 XX-85-070-OO3 EN20406 EN21303 EN20601 IN-8 5-886-NO4 EN22303 OP30704 IN-85-984-001 OP30713 XX-85-071-N05 OP30713 IN-86-077-OO1 EN20703 XX-85-077-002 EN20601 IN-86-090-OO1 EN20901 XX-85-077-XO4 C011200 EN20902 IH60300 QA80608 XX-85-120-006 C011200 IN-86-108-001 QA80503 XX-85-122-039 MP71011 QA80511 IN-86-173-OO1 EN21506
. 1
.- VI~, Catee rv - Electrieml Design Key Words: Ampacity-Analysis Calculation Circuit Design Diesel Electrical Distribution Instrument MCC Overload Penetration Short Voltage I
Concerns: I-85-128-NPS EN20106 WI-85-100-024 EN22800 EN20411 WI-85-100-037 EN20106 EN20501 WI-85-100-038 EN20104 EN20502 EN20404 EN20601 WI-85-100-041 EN20105 QA80303 EN20406 I-85-993-NPS EN23105 WI-85-100-043 EN20106 IN-85-009-001 C010900 EN20501 IN-85-029-OO2 EN20401 EN20502 IN-85-064-002 EN23502 EN20503 IN-85-103-NO4 EN20405 WI-85-100-046 EN20405 IN-85-207-001 EN23803 WI-85-100-047 EN20405 IN-86-209-010 EN20402 WI-85-100-055 EN20406 IN-86-232-OO2 EN23803 XX-85-062-001- QA80503 IN-86-254-OO4 EN24200 QA80511 IN-86-254-005 EN24000 XX-85-077-002 EN20601 IN-86-266-003 EN23801 XX-85-122-OO4 OP30202 IN-85-313-001 EN23801 XX-85-122-005 OP30202 IN-85-506-001 EN23801 XX-85-122-027 EN24000 IN-85-519-001 EN23803 XX-85-122-028 EN24000 IN-85-734-001 EN23801 XX-85-122-029 EN24000 EN23803 XX-85-122-030 EN24300 IN-85-749-OO1 EN23504 EN21301 IN-85-832-001 EN23801 XX-85-122-031 EN24300 EN23803 EN21301 l IN-85-886-N04 EN22303 XX-85-122-032 EN21301 IN-85-919-001 EN23803 EN24300 1 IN-86-034-001 EN23801 XX-85-122-033 EN22800 IN-86-073-002 OP30804 XX-85-122-034 EN22800 W8P-86-025-X02 EN20405 XX-85-122-035 EN22800 WI-85-091-015 EN20403 EN22007 WI-85-100-009 EN24000 WI-85-100-010 EN21301 EN24300 WI-85-100-019 EN20103 EN20104 EN21303
~ .-~~,,-,--,,--,,-nn---,--w--
. VII. Category - Opermtirnal R adiness Key Words: 79-18 ALARA CCW CECC Drill Emergency ERF Evacuation Excerise Fuse Hardware Ir.volvement Isolation Leakage Maintenance NCR NUREG-0737 Operating Operation Operator Performance Pipe Support Post-Mod Post-Modification Qualification Radiclogical Readiness REP Requal Simulator SPDS Test Training Transmitter Concerns: BFN-85-001-001 OP30712 DHT-85-003 OP30803 EX-85-027-001 EN23001 HI-85-084-N05 QA80311 I-86-238-SQN OP31104 IN-85-055-NO4 C017100 IN-95-097-016 MP70702 IN-85-110-004 EN20503 EN21201
. VII. Category - Operrtional R adiness (Continued)
IN-85-142-006 OP30302 SQM-86-009-OO9 IH60400 IN-85-148-001 EN20405 MP71814 IN-85-220-OO1 OP30501 SQN-86-001-001 EN21804 IN-85-281-003 OP30302 SQN-86-002-001 EN21804.
IN-85-289-001 OP31002 SQP-86-OO9-OO2 OP31104 IN-85-323-OO1 OP30102 SQP-86-009-004 OP30801 IN-85-332-001 EN23702 SQP-86-OO9-005 MP71815 IN-85-400-001 OP30111 SQP-86-009-X03 QA80202 IN-85-617-001 OP30501 TAK-86-OO7 OP30711 IN-85-706-OO1 WP47-SQN WBN-0065 OP31105 IN-85-767-006 OP31002 WBN-233 OP30706-IN-85-795-N04 C017300 WI-85-060-001 OP31002 IN-85-833-001 CO10300 WI-85-100-003 OP30102 IN-85-841-001 OP30301 WI-85-100-018 EN21302 IN-85-894-001 OP31002 WI-85-100-034 EN20302 IN-85-933-010 OP31001 EN20303 OP30709 IN-85-955-001 OP31211 XX-85-OO1-001 OP30706 IN-86-014-001 OP30705 XX-85-022-OO1 OP31001 IN-86-055-OO3 OP31003 XX-85-026-001 OP31104 IN-86-077-001 EN20703 XX-85-027-XO3 QA80000 IN-86-208-001 OP30705 XX-85-031-001 SF91204 IN-86-209-003 EN20405 XX-85-048-OO2 OP31002 IN-86-209-012 OP30905 XX-85-053-001 C011100 IN-86-209-013 OP31002 XX-85-053-002 C011100 IN-86-282-004 C017100 XX-85-057-002 MP71707 IN-86-285-001 OP30101 XX-85--058-OO1 OP30708 IN-86-306-001 OP30501 XX-85-063-001 OP31104 IN-86-316-XO9 OP30802 XX-85-065-OO1. I-85-750-SQN JAM-86-OO1 OP31102 XX-85-067-OO1 OP31001
. JLH-86-OO4 OP30707 XX-85-069-001 OP31002 JMA-85-OO1 OP31104 XX-85-093-001 OP31002 4 OE-qMS-8 .C010400 XX-85-093-002 OP31002 EN22203 XX-85-093-OO3 OP31002-RII-85-A-0064 OP31104 XX-85-094-013 EN21002 RII-86-A-0095 OP31211 XX-85-116-OO3 OP30711 RII-86-A-0116 OP30501 -XX-85-116-014 OP30711 SQM-86-002-003 MP70605 XX-85-122-008 OP30102 SQM-86-009-008 MP70601 XX-85-122-OO9 OP30102 QA80303 XX-85-122-010 OP30102 QA80307 XX-85-122-036 OP30708 XX-85-122-039 MP71011 I
VIII. Category - Cabl* Tr v Supports Key Words: Base Plate Cable Tray calculation Category I Diesel i ECN L6509 Overaize Seismic Support ZPA Concerns: IN-85-037-OO1 C0113OO IN-86-262-OO5 EN23803 IN-85-055-OO2 C011305 IN-86-262-005 C011307 IN-85-103-001 C011301 IN-86-266-006 C010900 IN-85-109-XO4 C011301 IN-86-294-002 C011300 IN-85-186-OO3 EN23803 NAS-86-005 EN22405 IN-85-285-OO1 C011300 NS-85-OO1-001 WP-02-SQN-R1 IN-85-285-002 C011300 OW- 85-007-002 EN23803 IN-85-312-OO1 EN23803 PH-85-OO3-023 EN23803 IN-85-432-002 EN23803 SQP-85-OOS-001 C0113OO IN-85-519401 EN23803 SQP-85-005-002 C011300 IN-85-532-006 QA80208 SQP-85-005-OO3 C011305 WP-19-SQN-R1 SQP-85-005-004 C011300 IN-85-688-N05 EN23803 SQP-85-005-005 C011300 IN-85-734-OO1 EN23803 SQP-85-OOS-006 C011305 IN-85-798-004 EN23803 SQP-85-005-007 C011300 IN-85-856-003 EN23803 WI-85-100-011 EN23803 IN-86-028-002 EN23803 WI-85-100-015 EN23803 IN-86-140-002 C011300 XX-85-010-001 C011300 IN-86-200-003 C011300 XX-85-053-OO1 C011100 IN-86-238-003 EN23803 XX-85-053-002 C011100 IN-86-259-005 C010900 IX. Category - Tech Spec Revisions Key Words: Breaker Delta Diesel Flow Surveillance Technical UHI Concerns: IN-85-457-OO1 OP30701 IN-86-014-001 OP30705 IN-86-208-001 OP30705 IN-86-209-003 EN20405 SQP-86-OO9-XO3 EN80202
X. C-tegsrv - Corpornto Activities Key Wordsi Commitment Corporate Evaluation INPO
- Management Oversight Policy Tracking
. TVA Board
, Concerns: BEM-85-001-OO1 WP-16-SQN WI-85-100-034 EN20302 BFM-85-OO1-OO1 WP-16-SQN EN20303 IN-85-767-005 QA80102- _
0P30709 QA80605 WI-85-100-041 '
. EN20105 IN-85-977-001 OP30901 EN20406 s
IN-86-087-002 QA80102 - XX-85-026-OO1 OP31104 QA80106 XX-85-027-X05 MP70601 PH-85-056-XO2 QA80102 XX-85-053-XO3 MP70802 QA80110 XX-85-057-OO1 MP71706 SQM-85-OO1-001 WP-16-SQN XX-85-057-OO2 MP71707 WBM-85-001-OO1 WP-16-SQN XX-85-064-001 MP71702 l WI-85-086-OO1 QA80102 XX-85-077-OO3 NP70601 QA80110 XX-85-113-001 QA80102' WI-85-086-004 QA80102 QA80110 QA80110 XX-85-116-OO3 OP30711 WI-85-090-OO1 QA80102 XX-85-116-011 QA80101 QA80106 QA80102 WI-85-090-002 QA80102 QA80105 QA80110 QA80107 XX-85-122-048 MP71012 XI. Category - QA Program Key Words: 10 CFR 50
!. Appendix B ,
l Audit CAQ Corrective Action DNQA Finding i Nonconformance NQAM
! Procedures i Program QA Quality Assurance Topical 4
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XI. ;C-togsrv - QA Progrra (Continutd)
Concerns: BEM-85-OO1-OO1 WP-16-SQN WI-85-086-001 QA80102 BFM-85-001-001 WP-16-SQN QA80110 BFM-86-002-OO1 QA80101 WI-85-086-OO3 QA80102 QA80109 QA80110 BFNIESC-85-03 OP30713 WI-85-086-004 QA80102 QA80000 QA80110 EX-85-023-001 MC40703 WI-85-090-OO1 QA80102 I-85-761-NPS EN20704 QA80106 IN-85-213-001 C010900 WI-85-090-002 QA80102 IN-85-398-OO2 EN22301 QA80110 IN-85-688-OO2 QA80401 XX-85-027-XO7 IH60400 QA80404 QA80000 IN-85-688-OO4 QA80401 XX-85-050-001 0017300 QA80201 QA80404 QA80202 IN-85-767-005 QA80102 XX-85-050-002 C017300 QA80605 XX-85-050-OO3 C017300 IN-86-011-OO3 QA80101 QA80201 QA80104 QA80202 IN-86-087-002 QA80102 XX-85-102-010 QA80402 QA80106 QA80412 IN-86-087-003 QA80404 XX-85-113-001 QA80102 OE-QMS-1 QA80101 QA80110 PH-85-056-XO2 QA80104 XX-85-116-008 QA80101 QA80102 QA80114 QA80110 XX-85-116-011 QA80101 SQM-85-OO1-001 WP-16-SQN QA80102 SQM-86-002-004 QA80402 QA80105 WBM-85-OO1-OO1 WP-16-SQN QA80107 WBM-86-004-OO2 QA80101 XX-85-118-OO1 QA80102 i
QA80109 QA80106 XX-85-119-001 QA80102 QA80110 XII. Category - Superheat Transient Following HELB Key Words: AA l Analysis l Analyze Analyzed Anchor Break Cobra I Core Dead Weight Expansion j Fatigue 1
1 l._.._. _ _ .. _ ____________ _ _ _ _ _ _ _ _ . _ . . . . _ _ _ _ . ._,.., _
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- XII. Category - Superhe~t Tr nsient Following HELB (Continued)
FMEA Heat HELB Ice Sometric MSLB NUREG-1061 Steam Superheat Temperature Thermal Transient Valve Vault Concerns: None XIII. Category - Cable Pulling Xey Words: Bends Cable CBL Pull Radii Radius Sidewall Concerns: EX-85-076-003 C010900 IN-85-832-001 EN23801 EX-85-086-001 C010900 EN23803 EX-85-157-002 C010900 IN-85-856-004 C019200 HI-85-113-NO2 C010900 IN-85-856-005 C010900 C011300 IN-85-919-001 EN23803 I-86-101-SQN QA80203 IN-85-935-001 C010900 IN-85-018-004 C010900 C015100 IN-85-112-001 OP30401 IN-85-978-OO1 C010900 IN-85-138-001 C019200 IN-86-028-001 C010900 IN-85-201-OO3 C019200 IN-86-034-001 EN23801 IN-85-207-001 EN23803 IN-86-199-001 C010900 IN-85-213-001 C010900 IN-86-201-001 C010900 IN-85-255-001 C010900 IN-86-206-001 EN23801 IN-85-295-003 C010900 IN-86-259401 C010900 IN-85-300-002 C010900 IN-86-259-004 C010900 IN-85-313-001 EN23801 IN-86-262-003 C010900 IN-85-325-005 C010900 IN-86-266-006 C010900 IN-85-367-001 EN23801 IN-86-310-001 EN23801 IN-85-433-002 C010900 JLH-86-002 C010900 IN-85-436-004 C010900 XX-85-008-001 C010900 IN-85-506-001 EN23801 XX-85-094-004 C010900 IN-85-581-001 C010900 XX-85-094-005 C010900 IN-85-733-001 C010900
- XIV. Catee'>ry - Tech. Spec. Surv9111rnes Key Words: Snubber Specification Surveillance XI Concerns: IN-85-288-OO1 C011100 IN-85-457-OO1 OP30701 IN-86-014-OO1 OP30705 IN-86-208 @ 1 OP30705 IN-86-209-OO3 EN20405 SQP-86-OO9-XO3 QA80202 XV. Category - Other Technical Issues Key Words: Appendix R Chloride Compression Ferrule Fire Firewatch Fittings Fluoride Heat Lighting Material Procurement Purchase Purchased Purchasing Redundant Sense Line Separation Slope Sprinkler Substituto Teflon Traceability Tube Tubing Veret
e xy, Cr.tegnry - Oth*r Technicel Issuss (Continued)
Concerns: BNPQCP10.35-1 EN23106 WI-85-008-002 MC40703 DHT-8 5-003 OP30803 WI-85-036-002 MC40203 EX-85-023-001 MC40703 MC40510 EX-85-181-001 MC40201 WI-85-041-001 WP-01-SQN NC40301 WI-85-053-004 WP-01-SQN IN-85-010-004 EN23101 WI-85-053-011 MC40206 IN-85-119-001 C017300 WI-85-100-004 EN24200 IN-85-197-001 C017300 WI-85-100-024 EN22800 IN-85-218-001 C017300 WI-85-100-040 MC40401 IN-85-272-004 EN24000 MC40410 IN-85-291-001 MC40307 XX-8 5-02 7-X02 MC40705 IN-85-311-008 OP30601 MC40703 IN-85-339-002 MC40307 XX-85-033-006 IH60400 IN-85-443-002 MC40405 QA80000 IN-85-534-001 EN23101 XX-85-046-001 0017300 IN-85-534-002 EN23101 XX-85-048-002 OP31002 IN-85-545-XO7 MC40703 XX-85-050-001 C017300 IN-85-624-003 MC40307 QA80201 IN-85-660-001 NC40703 QA80202 IN-85-795-OO1 C017300 XX-85-050-OO2 C017300 IN-85-795-N04 C017300 XX-85-050-003 C017300 IN-85-948-002 OP30807 QA80201 IN-85-964-003 MC40201 QA80202 IN-85-977-001 OP30901 XX-85-068-006 WP-01-SQN IN-86-011-003 QA80101 XX-85-096-003 MP71101 QA80104 Xx-85-120-003 MC40512 IN-86-150-001 WP-01-SQN XX-85-122-011 EN24200 IN-86-167-001 WP-01-SQN XX-85-122-012 EN24200 IN-86-208-001 OP30705 XX-85-122-013 EN24200 IN-86-294-002 C011300 XX-85-122-033 EN22800 IN-86-305-002 EN23104 XX-85-122-034 EN22800 IN-86-314-004 EN24200 XX-85-122-035 EN22800 JAM-85-001 C017300 XX-85-122-042 QA80109 JHL-85-004 EN24102 QA80504 OE-QMS-1 QA80101 XX-85-122-045 M"A0401 QA80104 MC40410 PH-8 5-OO1-002 C017300 XX-85-122-046 MC40401 PH-85-002-027 C017300 MC40410 RII-86-A-0095 OP31211 XX-85-122-047 MC40401 SQP-85-004-003 MC40307 MC40410 SQP-86-001-001 0017300 XX-85-125-006 QA80201 WBN-233 OP30706 QA80202 i
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