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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 CH ATTANOOGA. TENNESSEE 374o1 400 Chestnut Street Tower II February 7, 1980 Director of Nuclear Reactor Regulation Attention: Mr. L. S. Rubenstein, Acting Chief Light Water Reactors Branch No. 4 Division of Project Management U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Rubenstein:
In the Matter of the Application of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 On February 6, 1980, IVA received an informal request from the NRC for the following additional information on the Shift Technical Advisor (STA) and the Technical Support Center (TSC).
Shift Technical Advisor
- 1. Type and extent of traini g for the short term
- 2. Qualification of STA applicants
- 3. Responsibilities and duties of the STA
- 4. Duties of the Nuclear Experience Review Panel (NERP)
- 5. Communication between the STA and NERP Technical Support Center Means for ensuring that employees in the TSC had access to the various plant parameters in response to the NRC request, the fallm?ing information is being forwarded for NRC review.
Shift Technical _ Advisor The qualification of STA's and their responsibilities and duties are specified in the enclosed TVA Division Procedures Manual (DPM No. N7A15). Another Division Procedures Manual (DPM No.
N72A39) is enclosed which provides the requested information o.1 NERP. This DPM is in draft form and will be revised to specify that appropriate licensee event reports will be sent from NERP to the STA, Plant Operations Staf f, and the training center.
The short-te rm training for STA included 112 hours0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br /> of academic \
training an. 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of simulator training.
\
1951 001 An Equal Opport Employer
@0 M20 $O
Director of Nuclear Reactor Regulation February 7, lH 3 Academic Training Technical Specifications, Safety Analysis Report, Operating Instructions, Abnormal Operating Instructions, Reactor Coolant System, Chemical Volume Control System, Residual lleat Removal System, Primary / Secondary Containment, Ice Condensers, Contain-ment Spray Systems, Bbin Steam and Steam Dump Systems, Condensate System, Feedwater and Auxiliary Feedwater Systems, Emergency Raw Cooling Water Sy< tem, Component Cooling Water System, Reactor Protection System, Engineered Safety Features Actuation System, and Site Radiological Emergency Plan Simulator Training Thirty hours of normal operations including startup, shutdos., and power ascension Thirty hours of abnormal operations including accident analyses recogni-tion, instrument failure, and degraded core operation Technical Support Center To ensere that TSC employees have access to control room information, a porcable closed circuit television camera will be stored in the TSC. During an emergency, a hand-held camera will be maintained in the control room to relay pictures of the control room to a monitor located in the TSC. Communications between the TSC and the control room are availabic to ensure that the camera is focused on the appropriate monitors as requested by TSC staff.
Very truly yours, TENNESSEE VALLEY AUT110RITY m:
L.' M. Mills, Manager Nuclear Regulation and Safety Enclosures 1951 002
.- r- DRAFT
.. JH:CLT .
8 1/21/80 ENCLOSURE Those listed J. R. Calhoun, Director of Nuclear Power, 716 EB-C REVIEW OF NUCLEAR PLANT OPERATING EXPERIENCE REPORTS - DPM N72A39 1.0 Purpose TVA's nuclear program can benefit from the operating experience of other nuclear plants if we systematically and conscientiously review sources of industry operational information. This review can detect pctential problems before they occur at a TVA plant and find new ideas for solving existing problems and improving plant operation. This division procedure establishes a system to ensure review of operating experience reports, to document their applicability to TVA plants, to ensure proper disposition of all applicable items, and to provide periodic discussion of interdisciplinary and major technical problems among responsible division management.
2.0 Nuclear Experience Review Panel A Nuclear Experience Review Panel (NERP) shall be f ormed to oversee the implementation of this procedure. The panel shall consist of the following members:
Chairman, Assistant to Director (Programs & Administration)
Members, Chief, Reactor Engineering Branch Chief, Controls and Test Branch 1951 .
003
Chief, Nuclear Maintenance Branch Chief, Outage Management Branch Supervisor, Design Review Staff Supervisor, Nuclear Operations Staff Supervisor, Reliability Programs and Planning Staff Supervisor, Quality Assurance Staff Representative, Division of Engineering Design Representative, Office of Power Quality Assurance Staff Secretary, _apervisor, Management Compliance Unit The panel shall meet at least quarterly as scheduled by the Chairman.
An agenda for each meeting will be developed by the Chairman and sent to each member approximately two weeks prior to the meeting. In developing the agenda, the Chairman should consider the following categories for topics of discussion:
- 1. A general review of problems in meeting the requirements of this procedure.
- 2. NERP items of an interdisciplinary nature which should receive attention from or could be of interest to the entire panel.
- 3. Sbjor technical issues facing the nuclear industry (whether they are NERP items or not).
- 4. Fhjor problems experienced at TVA plants which could be of interest to or eventually affect organizations other than the responsible one.
1951 004
Memberc of NERP may be assigned responsibility for presentations on particular topics at the meetings. These assignments will be shown on the agenda. Other supervisors within NUC PR or other TVA organizations may be invited to make presentations on major technical issues. Members should review and be prepared to answer questions on open NERP items assigned to their respective organizations.
3.0 Dissemination of Material The NERP Secretary is responsible far dissemination of operating ex-perience information for review by the technica) staffs and branches.
The following sources of information shall be received by NERP Secretary and distributed to the appropriate organizations for review.
NRC Inspection and Enforcement Operatinn Experience NRC Current Events, Power Reactors Nuclear Power Exnerience Nuclear Safetv Vendor information letters NRC Inspection and Enforcement - Bulletins to plant superintendents NRC Circulars NRC Information Notices EPRI Reports - Technical Summaries Additionally, all division supervisors and engineers, who periodically read industry trade journals, attend technical meetings, or communicate with vendors, other nuclear utility personnel, or any other nuclear industry representatives, should look for operational problems which 1951 005
could affect TVA's nuclear plants and also new ideas or proposals which could improve the operation of TVA's nuclear plants. Any items which fit this description should be sent to the NERP Secretary for distribution to the appropriate organizations for review.
4.0 Review of BSterial All material distributed by the NERP Secretary requires a prompt review within the assigned organization. This review shall consider whether each assigned item could be applicable to any TVA nuclear plant, even if it is still under construction. A written response shall be made to the NERP Secretary concerning the applicability of each item with a brief justification. ,
An item which is determined to be app 14 cable to a TVA plant will be assigned a unique number as described in Section 5.0 and tracked until its final disposition. For nonapplicable items, the justification may contain nothing more than "this equipment (or design) is not found in TVA plants" but, in any case, must be adequate to indicate that the problem has been invectigated. For example, "we wou.d not operate the system in such a manner" is not an adequate justification but "the RRR operating procedure (01-74) for Browns Ferry which is the only TVA plant with a similar system prohibits operation in the mode described in the LER" is an adequate justification for nonapplicability of an item.
1951 01D6 In addition to indicating the applicability of each item, the reviewer should recommend in his response to the NERP Secretary whether the
item should be sent to the nuclear plants for information, and, if so, which plants. The fallawing types of items should generally be sent to the plants:
- 1. Descriptions of problems involving or resulting from operator error.
- 2. Significant transient events whether caused by equipment failure, operator error, or any other reason.
- 3. Operational problems which resulted from equipment failure if the equipment is similar to that in a TVA plant.
The NERP Secretary shall maintain a tracking system to ensure that a response is received on all iters distributed for review. If a response is not received within one month of initial distribution, the NERP Secretary shall send periodic followup notices to the responsible organization with copies to the Chairman, Nuclear Experience Review Panel until the response is received.
1951 007 5.0 Trackine and Disposition of NERP Items When the review of an item, as described in Section 4.0, determines that it is applicable to a TVA nuclear plant or the JVA nuclear program in general, the item shall be assigned a unique number by the NERP Secretary and shall be entered into the NERP item tracking system which will be maintained by the NERP Secretary. The tracking system shall contain a brief description of the item, the source of the item, the person responsible for the item, and a section for updating the resolution
a6-status of the item. The NERP Secretary shall ensure that the open NERP items list is updated quarterly, approximately two weeks prior to the scheduled NERP meeting. A copy of the updated open NERP items list will be sent to NERP members for review several days prior to the scheduled meeting.
Prompt resolution of NERP items is the responsibility of the technical organizations with NUC PR. They shall obtain information from the plants and assistance from EN DES, vendors, or other TVA organizations as necessary to ensure satisfactory resolution of assigned items. When the solution has been determined for a NERP item, the assigned technical organization is then responsible for implementation of any necessary changes. This implementation may be in the form of a division procedure, a design change request, or other appropriate means. A memorandum shall be written to the Chairman, NERP documenting and justifying the resolution and implementation of changes on all NERP items. The ,
Chairman shall review and approve the justification before the item is closed.
1951 008
ENCLOSURE Page 1 N79A15 F TENNESSEE VALLEY AUT110RITY Division of Nuclear Power P Division Procedures Manual To: Assistant Director (Operations)
Assistant Director (Maintenance and Engineering Services)
Plant Superintendents, All Nuclear Plants
" Chief, Nuclear Training Branch f Chief, Reactor Engineering Branch From: J. R. Calhoun, Director of Nuclear Power 9
Subj ec t: Sil1FT TECllNICAL ADVISOR (STA) - DPM NO. N79A15 F
References:
- 1. NUREG-0578, "IMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations," dated July 1979 F 2. Memorandum to All Operating Nuclear Power Plants from
~
Harold Denton, Director, NRR, NRC, " Discussion of Lessons Learned Short-Term Requirements," undated--received by y the Division of Nuclear Power the week of October 29, 1979 1.0 Purpose This procedure describes how the requirements for t'm Shift Technical 5" Advisor (initially presented in reference 1 and clarified in reference 2) will be met by TVA and assigns responsibility within the division for their implementation.
2.0 Assignment of Responsibility ]g {{}
2.1 The Assistant Director for Operations shall have overall responsibility for implementing all requirements associated F with the STA.
2.2 As assigned by the Assistant Directr. or Operations, the Reactor Engineering Branch shall uevelop a program plan for F meeting the requirements for STA. This plan shall include specific management recommen.'/ tons to achieve the following:
- 1. Selection and training of personnel for STA to go on shift at Browns Ferry and Sequoyah Nuclear Plants by January 1, 1980.
- 2. Upgrading of training to meet full qualification requirements for STA by January 1, 1981.
7 The Reactor Engineering Branch shall have direct responsibility for working with the plant staffs to ensure that sufficient personnel exist to meet the requirements for STA. In plants n==
Page 2 N79A15 .
1/7/80 --
in which sufficient people do not exist, the Reactor Engineering Branch will take the lead in securing additional candidates cither from within TVA or by outside recruiting, rx.
The Reactor Engineering Branch shall develop the training =_; '
requirements and overall scope of instruction for the STA such that the Nuclear Training Branch can develop a training program.
2.3 Each plant superintendent shall have engineering positions on his plant staff designated for STA. The number of positions for each plant shall equal (5 + the number of units). At __
Browns Ferry and Sequoyah Nuclear Plants, each position shall %6 be filled by January 1, 1980, and fully trained by January 1, 1981 or fuel loading, whichever is later. Other STA positions should be filled in a timely manner based on expected issuance ---
of an operating license and training requirements. lie shall develop a shift rotation schedule to provide continuous shift coverage by an inplant STA who can be in the control room of ,,,
operating plants within 10 minutes of notification, lie shall ensure that personnel who serve ac, STA's meet the minimum qualification requirements as prescribed below.
2.4 The Nuclear Training Branch shall provide a training program ,__
which is operational by February 1; _ 1980, and which is capable of training engineers to meet the qualification requirements ,_.
for the STA by January 1, 1981, ot fuel loading, whichever is later. Specific training in the following areas will be necessary.
2.4.1 Nuclear Plant Systems a--
~
A. Basic Components s=.
B. Reactor Coolant System j]
C. Emergency Core Cooling Systems D. Residual lleat Removal Systems E. Containment Systens F. Control Rod Drive Systems G. Fuel llandling Systems ---
11 . Secondary Side and Auxiliary Systems 2.4.2 Power Plant Operation A. Startup B. Shutdown -
C. Power Operation ,-.
D. Integrated System Response
T'. .
Page 3 N79A15 1/7/80 0 2.4.3 Transients and Accidents A. Licensing Basis Transients and Accidents F
a 1. Assumptions
- 2. Conservatisms
- 3. Minimum equipment taken credit for B. Transient and Accident Recognition and Operatot Action
- 1. FSAR Chapter 15 events M
- 2. Instrumentation failures
- 3. Degraded conditions of system availability 2.4.4 Limiting Conditions for Operation A. Technical Specification Definition J. Technical Specification Bases 2.4.5 TVA Operational Practices A. Job Assignments and Responsibilities T B. TVA rbergency Plan y C. Document Familiarization D. Clearance Procedures
]
E. Plant Safety Practices and Procedures 2.4.6 The Nuclear Training Branch will also be responsible for providing an annual retraining program and F,,. schedule which will be coordinated with the central office and the plants by November 1, 1980.
3.0 Requirements Each nuclear plant will be staffed with a crew of trained engineers for continuous shift coverage who meet the following qualifications F; and who perform the following specific duties.
3.1 Qualifications for Personnel Filling the Positions of Shift Technical Advisor 3.1.1 By January 1, 1980 By January 1, 1980, or by issuance of ar e operating license, whichever is later, individuals who~ fill P the positions of Shif t Technical Advisor (STA) shall satisfy the following minimum qualifications.
.A
. Page 4 N79A15 1/7/80 __
- 1. Must have a bachelor's degree in nuclear engineering or the equivalent.
- 2. Must have qualified as a shift nuclear engineer under the respective plant nuclear engineer __
training program. ._ ,
- 3. Must have received a minimum of traintag in each of the following areas.
- a. Transient and accident recognition and operator action. __
- b. Limiting conditions for operation and their h""
bases
- c. TVA Radiological Emergency Plan
- d. Shif t assignments and responsibilities ,
3.1.2 By January 1, 1981 By January 1, 1981, or by ssuance of an operating e.,,
license, whichever is lat , individuals who fill the positions of Shift Tc inical Advisor (STA) shall satisfy the following minimum qualifications.
- 1. Must have a bachelor's degree in nuclear engineering or the equivalent.
^
- 2. Must have qualified as a shift nuclear engineer training program.
- 3. Must have successfully completed all training described in section 2.4.
- 4. Must have been certified by a panel consisting of the following:
- a. A licensed SRO 1 012,
- b. Representative cf the Reactor Engineering Branch
- c. Representative of Nuclear Operations Staff 3.2 Duties of the Shift Technical Advisor ,.,
STA duties shall consist of the following:
- 1. Control room advisor to the shift engineer on off-normal [C[
events. This includes analyses and preparation of scram reports.
- 2. Advisor to the shift engineer on allowable conditions for inoperable equipment and equipment out of service.
- p. . .
f.. . . Page 5
. N79A15 1
. 3. Advisor to the shift engineer on operating experience fr/7/80 om F
other plants.
p 4. Advisor to shift engineer as requested on unscheduled maintenance of equipment and post-maintenance testing (this duty will become effective January 1, 1981).
3.3 Retraining for Shift Technical Advisor -
Each Shif t Technical Advisor will cc n,lete a retraining program annually consisting of classroom and s.mulator time as well as i continuous updating on plant procedures.
4.0 Implementation
.:f The following assignments are made for the purpose of implementing the requirements of Shift Technical Advisor.
4.1 Chief, Nuclear Training Branch 4.1.1 The requirements of Section 2.4 are directed at developing a fully qualified Shift Technical i Advisor by Janum 1, 1981, at the operating plants.
Toward this object.ive, you are requested to submit to the Assistant Director for Operations by February 1, 1980, a training plan which defines the scope of training center and inplant instruction and which gives an overall schedule for trair.ing Browns Ferry and Sequoyah personnel during calendar T year 1980. The complete training program should be submitted for review to the Assistant Director g,. for Operations by February 15, 1980.
4.1.2 The qualifications given in section 3.1.1 - (3) describe the minimum training requirements for STA which must be met by January 1, 1980. Recognizing that those engineers who serve as STA's on January 1, 1980, will basically come from existing plant personnel, assess immediately the availability F. of both PWR and BWR short courses to provide a part of this training. These courses will be needed between now and January 15, 1980, in order for TVA to meet their near-term commitments for STA.
4.1.3 An annual retraining program as required by section 3.3 for the Shift Technical Advisor should be F" suLmitted for review to the Assistant Director for Operations by November 1, 1980.
F 4.2 Chief, Reactor Engineerir.g Branch 1951 013 4.2.1 The requirements of section 2.4 are directed at developing a fully qualified Shift Technical Advisor by January 1, 1981, at the operating plants. Toward P
this objective, you are requested to provide direct assistance to the Chief, Nuclear Training Branch in formulating the content of this training program.
Page 6 N79A15 1/7/80 4.2.2 The qualifications given in section 3.1.1 - (3) describe ___
the minimum training requirements for STA which must be met by January 1, 1980, et the operating plants. To augment the Nuclear Training Branch's presentation of --'
short courses towards meeting this objective, you are requested to work closely with the Chief, Nuclear Training Branch, in contacting the appropriate orgaal-zations in Westinghouse and General Electric to obtain __.
additional near-term training in the fundamentals of plant transients and transient recognition.
Toward meeting the objective: 1. manning the STA 4.2.3 positions by January 1, 1980; 2. continuing to provide p.,i station nuclear engineering and startup testing support; and 3. providing the training required to meet the ,_.
January 1,1981, requirements, you are requested to work closely with the plant superintendents to determine how nuclear engineers currently on, or assigned to, the plant staffs can best be utilized. You are re- """
quested to take the lead in recruiting additional manpower as needed.
4.3 Superintendents, Nuclear Power Plants 6^-
4.3.1 Appendix I contains the job description for the position of Shift Technical Advisor. We request that immediate steps be taken to advertisc and fill JTA positions at Browns Ferry Nuclear Plant and Sequoyat Nuclear Plant; other STA positions should be filled in a timely manner ,_.
based on expected issuance of an operating license and training requirements.
4.3.2 To meet the qualification requirements of 3.1.1 - (2) and 3.1.2 - (2), you are requested to develop and implement an inplant qualification program for nuclear engineers assigned to shift coverage. This qualification program should include but not be limited to training in the following areas:
4.3.2.1 General Areas """
- 1. Plant orientat- in and familiarization
- 2. Review of plant manuals, instructions and drawings
- 3. Overview of plant systems - ==*
4 Plant testing and inspection programs (surveillance, ASME - Inservice, pumps and valves; initial startup or startup b following refueling; and balance of plant survel .cnce) one
4 Page 7 N79A13 1/7/80
- 5. General employee training (instructions -
gj preparation, use and control; security, health physics, etc.)
4.3.2.2. Specific Areas
- 1. Reactor coolant systems f amiliar; zation
- 2. Reactor protection / control systems familiari-zation m
-- 3. Reactivity control systems familiarizatien
- 4. Emergency core cooling systems familiarization
- 5. Nuclear instrumentation systems (SRM, IRM, PR, and incore systems (fixed and movable))
familiarization f
- 6. Nonnuclear instrumentation (NSSS thermal . i hydraulic monitoring) familiarization
- 7. Core monitoring with respect to safety limits and their relationship with reactor protection r 8.
system design requirements, reactor protection system setpoints, and technical specifications Familiarization with vendor core follow and/or
- fuel management methods including fuel warranty requirements or recommendations
- 9. Special nucleat materials control, accountability, T. and licensing
- 10. Fuel and core component handling (incore and i; out-of-corc)
- 11. Computers familiarization (Online - Offline process and digital)
- 12. Familiarization of NSSS vendor-supplied computer software anNor offline computer software for core monitoring nr analysis
- 13. Familiarization with the general operating instructions for startup, normal operation, f and shutdown
- 14. Other topics could include vendor methods for reduction of incore instrumentatica data, cycle
{ length predictions, reactivity balances, and process computer nuclear performance calculations F
1951 015
Page 8 N79A15 1/7/80 __
t,,3.3 Becwns Ferry . ;1nt and Sequoyah Nuclear Plant -
Given your cu'. /els of inplant personnel who meet tSe educationa. au shift nuclear engineering qualifi- --
cation requirements, develop a schedule for the release of there personnel during 1980 for Training Center in-struction recognizing that the STA function must be _
continucusly met. Identify to the Chief, Reactor __. ,
Engineering Branch, your major problems in this area as soon as possible.
Other plants - Given your levels of inplant personnel who meet the educational and shift nuclear engineering quall-fication requirements, develop a Lehedule for the releanc __
of these personnel for Training Center instruction recog-nizing the STA function must be met before issuance of an kU' operating license. Identify to the Chief, Reactor Engineering Branch, your plans and major problems in --
meeting the requirementsiof this DPM by January 15, 1980.
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TDK:MLG Attachment pm
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FMME 1951 016 ._.
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Page 9 N79A15 1/7/80 0 Reactor Engineer / Shift Technical Advisor SD-4 F
u Supervision Received Under the direct supervision of the Power Plant Results Supervisor, grade M-5, who defines the scope of work and the results expected and reviews progress within the guidelines. Proceeds independently in accordance with outlined plans, standard practices, license requirements, r and plant instructions. While serving in the capacity of shif. technical advisor, he is under the functional supervision of the shif t engir.eer responsible for his assigned shift.
Duties and Rosponsibilities Performs responsible professional engineering work in nuclear safety, plant fuel manage:.ent, and nuclear plant equipment performance.
May be assigned to a specific nuclear unit as unit cognizant reactor engineer. In this capacity, he performs the following duties and responsibilities.
Develops control requirements for optimum core power distriLution consistent with fuel management requirements. Directs and develops on-yo line and off-line computer application in areas such as core performance and fuel warranty. Prepares detailed plans for reactor refueling and r subsequent testing requirements for plant startup. Reviews operating and replacement criteria for in-core detectors, control rods, flow orifices, and neutron poisons. Reviews applicable nuclear surveillance testing and evaluates results. Reviews plant operating data and reco cends P necessary action to prevent or correct any condition that may affect
.a the safe, reliabje, and efficient operation of the plant. Prepares detailed maneuvert and applicable documentation for fuel and saurce handling. Maintain cognizance of nuclear systems which may affect the safety of the plant. Provides technical guidance to operations personnel to minimize impact of systems taken out of service for scheduled maintenance and post-maintenance testing.
May be assigned shif t coverage as a shif t technical advisor. In this capacity, he performs the following duties and responsibilities.
Provides advice as requested by th shift engineer in the event of an accident or i. aormal operational condition. Provides advice as requested by the shift engineer on allowable conditions for inoperable equipment and equipment out-of-service. Evaluates the operating history of the F- plant (equipment failures, design problems, operations errors, etc.)
and Licensee Event Reports from other plants of similar design with suitable dissemination of the results of such evaluations to other F members of the plant staff. Acts as an advisor to shift engineer as requested on unscheduled maintenance of equipment and post-maintenance testing. Performs engineering evaluation of continuing adequacy of plant operational quality assurance, plant operating procedures, and P" plant cmcrgency procedures. Maintains cognizance of current fuel integrity and evaluates the impact of plant operations on fuel performance.
Prepares reports as requested on plant status. Functions as the test engineer during initial startup and startup following refueling.
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Page 10 N79A15 1/7/80 '
Supervision Over Others Directs the work of lower grade employees who may be assigned to him.
Qualifications Shall have a minimum of a bachelor's degree in nuc. car engineering or ---
the equivalent and 4 years of applicable experienct related to the design or operation of a nuclear plant.
At least one year of the above 4 years' experience must be in-plant experience related to core performance calculations, core physics ht-testing, nuclear instrumentation calibration, in-core fuel management, and other station reactor engineer f unctions. ---
Shall have knowledge in the r.rea of fuel failure mechanisms and the detection of these mechanisms in the off-gas system, the reactor
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coolant se y system, and process radiation monitors.
Shall have extensive knowledge in the areas of plant response to transients and accidents and technical specification content with p"f emphasis on the bases for limiting conditions for operation.
Shall have significant training in plant systems and operating procedures,
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including reactor simulator training in transient and accident response.
14u s t have the ability to apply expertise in a coordinated effort with persons of various disciplines under both routine and emergency situations. .--
N SWWWEB M
M I951 0Ib,
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