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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 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 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 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 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 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 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 ML20206C0841999-04-23023 April 1999 Forwards Insp Repts 50-327/99-02 & 50-328/99-02 on 990214-0327.No Violations Noted ML20206C6541999-04-23023 April 1999 Forwards Response to NRC 990127 RAI Re GL 96-05 for Sequoyah Nuclear Plant,Units 1 & 2 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) 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 ML20205B1091999-03-19019 March 1999 Submits Response to NRC Questions Concerning Lead Test Assembly Matl History,Per Request 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:OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT TO NRC
MONTHYEARML20245G6611989-06-20020 June 1989 Forwards Sequoyah Nuclear Power Plant Exercise, Re 881214-15 Radiological Emergency Preparedness Plan Exercise. Seventeen Areas Requiring Corrective Actions Noted ML20209E6381987-04-17017 April 1987 Forwards Sequoyah Nuclear Power Plant Exercise Conducted on 861119. State of Tn & Counties of Hamilton & Bradley Fully Participated in Exercise.Areas Requiring Corrective Action & Areas Recommended for Improvement Noted ML20127J1281985-06-21021 June 1985 Forwards Sequoyah Nuclear Power Plant Exercise Conducted on 850206, Per Offsite Radiological Emergency Preparedness Plans.Five Deficiencies Observed Requiring Schedule of Corrective Action ML20091G4051984-05-25025 May 1984 Supports Request for Exemption of State & Local Govts from Participation in Annual Radiological Emergency Preparedness Exercise,Per & FEMA 840504 Memo Concurring W/State Request ML20077G2101983-07-29029 July 1983 Informs That Comments on Aquatic Environ Conditions in Chickamauga Reservoir During Operation of Sequoyah Nuclear Plant,Second Annual Rept (1982) Should Be Submitted within 30 Days ML20054F9601982-06-0202 June 1982 Forwards Tn Ofc of Civil Defense & Emergency Preparedness Evaluation of 800616-17 Offsite Emergency Preparedness Exercise W/Fema Observations.Fema to State Noting Deficiencies of 810707-08 Exercise Also Encl ML19345H2281981-04-23023 April 1981 Responds to 810310 Request for Findings & Determinations Re State Radiological Emergency Response Plan Approved by FEMA & Subj to Specified Conditions in 800807 Ltr to Nrc.Alerting & Notification Sys Under Review by FEMA Region 4 ML19337A4141980-08-0707 August 1980 Forwards Certification of FEMA Findings & Determination Re multi-jurisdictional Radiological Emergency Response Plan. FEMA Correspondence & Rept Also Encl ML19290E0921980-02-14014 February 1980 Discusses Emergency Planning & Preparedness Re Facility in Response to NRC 800214 Ltr.Nrc Recommendation for Licensing to Permit Low Power Testing Appears Reasonable Due to Potential for Accidents & Condition of Emergency Plans ML19296C4561980-02-11011 February 1980 Advises That Review of Emergency Plan Is Dependent on NRC Establishment of Low Power Licensing Criteria.Requests Action to Expedite Concurrence ML19309B6931979-12-13013 December 1979 Forwards Ak Bissell 791205 Ltr Encouraging Early Licensing of Facility & All Qualified Nuclear Plants.Requests Comments.Resolution Encl ML19250B9911979-11-0101 November 1979 Informs That No Endangered or Threatened Plant or Animal Species Are Found in Area ML19254D3141979-10-17017 October 1979 Responds to 791005 Request for Info Re Endangered Species in Vicinity of Proposed Transmission Line Const.Info Will Be Forwarded After Review by Asheville Area Ofc ML19207A7601979-08-14014 August 1979 Forwards 790629 Ltrs from Util to SW Harvey & Jc White of EPA Re Aquatic Monitoring Programs Including Proposed Amend to EPA License ML19259C0831979-06-0404 June 1979 Requests Comments & Recommendations Re Const Effects Monitoring Program,Semiannual & sediment-elutriate Repts. Requests Response by 790615 1989-06-20
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t ,J UNITED STATES ENVIRONMENTAL PROTECTION AGENCY
% m3/ REGION IV 345 CouRTLAND STREC ATLANTA GEORGI A 30308 AUG f 41979 REF: 4E-WE Director, Division of Site Safety and Environmental Analysis Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Voss Moore Director of Environmental Projects Re: TVA Sequoyah Nuclear Plant NPDES Permit No. TN0026450, Operational Aquatic Manitoring Program TVA Phippa Bend Nuclear Plant NPDES Permit No. TN0029301, Intske System - Fish Mitigation Devic -
Dear Sir:
Enclosed for your review are several pieces of correspondence we have received from TVA which concern their Aquatic Monitoring Programs at the two referenced facilities. Please provide any comments you may have to me.
We would appreciate receiving your comments within the next 30 days.
Sincerely yours,
.ioward D. Zeller Deputy Director Enforcement Division ec: Tennessee Department of Public Health Enclosures
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1 J.a 790822 d O?
a TENNESSEE VALLEY AUTHORITY
. CHATTANOOGA. TENNESSEE 374ot 268 hol Building RECk -
. LUNE 2 91979 EPAI E "
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UJ. 3 3 a ..rh.-i-EE.CE~3 DFASICH
, 84TQ,.T' r..ICnQ -,
[/ *Q,c.,Dj Mr. Sanford W. Harvey, Jr. , [], 'l,
. fb I Director, Enforce =ent Division !r i' U.S. Environ = ental Frotection Agency //ff.,"ryb20197g~ ;f Region IV I!- CQ , -
3h5 Courtland Street, NE. F 9,.! ; / ,
Atlanta, Georgia 30308 ff 10.2." 7;.- .
C1 Dea
SEQUOYAH UUCLEAR PLANT - NPDES PERMIT NO. TN0026h50 - OPPATIONAL AQUATIC MONITORING PROGRAM In accordance with Part I.B.l.f. and Part III.G. of the subject permit, enclosed is an amendment to the operational aquatic monitoring program.
The emendment describes additional data collection to docu=ent possible effects in i=pinge=ent due to change in operational code at the Sequoyah Nuclear PlaE.- "'
If you have any questions concerning this c=end=ent, please let te know.
S'ncerely, ,
,f Harry G. Moo e, Jr., Ph.D.
Acting Direc or cf Enviren= ental Quality Enclorare cc (Enclosure):
Tennessee Department of Public Health Mr. Charles H. Kaplan Division of Water Quality Control Coordinator, Them al Analysis Unit 621 Cordell Hull Building Enforcement Divisien Nashville, Tecnessee 37219 U.S. Environmental Protection Agency 3h5 Court h a Street, NE.
Mr. Jack McCormick, Regional Engineer Atlante., Georgia 30308 Division of Water Quality Centrol Tennessee Department of Public Health 2501 Milne Street Chattanocga, Tennessee 37hC6 50$0 An Eaual Opportunity Employer
/4!EICME';T OPERATIC!IAL MOIIITCRII!G P90GR/?:
SEQUOYAH I!UCLEAR PLAITT June 28, 1979 The potential for change in impingement due to change in operational.
- ode, resulting from elevated te=peratures of intake water, possibly containing chlorine in detectable a=ounts, vill be examined. Sampling
=ethodology for baseline i=pingement reference vill consist of three samples, each of eight hours duration, i==ediately prior to closed cycle operation. Upon initiation of closed cycle operation, sa=ples vill be taken at two-hour intervals until intake te=peratures have stabilized. This procedure vill be re; ,ited at least twice-in spring during rising water te=peratures, and in su==er during peak vater te=peratures. If possible, the reverse procedure of going fro = closed cycle to so=e other operating = ode vill be examined using similar sa=-
pling =ethodology. Sa=pling methodology and intervals =ay be revised so=evhat as dictated by operating constraints, persennel availability, and the analysis of early results of the invest fstion.
7840 7
TENNESSEE VALLEY AUTHORITY CHATrANOOGA. TENNESSEE 374ot 4
W 5' e JUN 2 91979 E.
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!?jl UUL Mr. John C. White
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Administrator, Region IV .j g ,W-(p' ~
- 7. ,1, ,
Environmental Protection Agency 345 Courtland Street, NE. -pRg h Atlanta, Georgia 30308 % 1. CA*
Dear Mr. White:
PHIPPS BEND NUCLEAR PLANT - INTAKE SYSTEM - FISH MITIGATION DEVICE Enclosed is TVA's conceptual program for monitoring the biological effects of the plant intake fish mitigation system for the Phipps Bend Nuclear Plant.
Included in the program are conditions for which the fish mitigation device will be bypassed.
TVA has recently announced slowdowns in the construction schedules at three nuclear plants (including Phipps Bend) pending a reexamination of projected power demands, schedules for completion of plants under construction, and other factors. It is expected that Phipps Bend's schedule may be adjusted such that unit 2 would begin commercial operatica several years later than unit 1. However, schedule delay options are still being analyzed and firm schedules are uncertain at this time. We intend to conduct the monitoring for the enclosed conceptual plan in ore continuous period beginning at com-mercial operation of unit 1 and extending until one year after commercial operation of unit 2. However, delay of unit 2 may make this impractical, and separate monitoring periods may be necessary. The enclosed conceptual monitoring program reflects this approach.
S$ncer21y, ,
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[
l W Harry G. Mo re, Jr., Ph.D.
Acting Dire}ctor of Environmentar Quality Enclosure cc: See page 2
.s.
An E iual Ononrtunity Fmni w
Mr. John C. White JUN 2 g 1979 cc (Enclosure):
Mr. Kenneth E. Black, Regional Director U.S. Fish and Wildlife Service 17 Executive Park Drive, NE.
Atlanta, Georgia 30329 Mr. Sanf d W. Harvey, ., Director Enforcemen Division, egion IV Environment 1 Prote - ion Agency 345 Courtlan St et, NE.
Atlanta, Geor 30308 Mr. Charle ap an, Coordinator Thermal alysis Unit Enfore ent Divis on Envir nmental Prot tion Agency 345 ourtland Street NE.
anta, Georgia 303 Mr. Earl Leming, Chief Knoxville Regional Office Environmental Health Services Dd g'*e33 1522 Cherokee Trail d Knoxville, Tennessee 37920 #
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2q Pr. Elmo Lunn, Director Division of Water Quality Control p Department of Public Health g.f,}
q 621 Cordell Hull Building g&,
Nashville, Tennessee 37219 ,
64'
\ / 6' Mr. Lee Tebo, Chief
%t Pollution Surveillance Branch U. S. Enviro'nmen'tal Protection Agency ['*n -1 College Sta' tion .ad Athens , , Georgia 30601 (N( T
,f';'
Director, Division of Site Safety and gW ~g Environmental Analysis Attention: Voss Moore, Director of (.
Environmental Projects Nuclear Regulatory Commission Washington, D.C. 20555 784C
Phipps Bend Nuclear Plant Conceptual Program for Monitoring the Biological Effects Of the Plant Intake System Described herein is the conceptual biological monitoring program for assessing the effects of the plant intake system nd for evaluating the effectiveness of the fish mitigation device at the Phipps Bend Nuclear Plant. This program will be impJ emented on or before the date of commercial operation for unit 1 and remain in effect for two years. Additional monitoring will be conducted to assess effects related to the addition of a second unit to this plant. During and after this monitoring, data will be analyzed and reviewed ta determine the need to modify the screen operating procedures and the need to continue the monitoring program. Program modifications and supporting rationale will be submitted to EPA at least 30 days prior to implementation.
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Fish Mitigation Device TVA plans to operate the fish mitigation screen facilities only during the period when significant numbers of larval fish are present in the Holston River in the vicinity of the plant. The beginning and end of this period will be determined by icth /oplankton occurrence data obtained during preoperational monitoring.
During periods when larval fish are not present in significant numbers, the mitigation device may be bypassed. In addition, any operating screen will
.utomat.4 ally be bypassed to prevent its collapse when a head loss of 18 inches occurs through the screen. In this event, a warning device in the control room will automatically be activated and measures will be taken to activate the redundent screen as soon as possible. The period of time the screen was bypassed and the volume of water drawn into the plant during this period will be documented. The screens will also be bypassed to provide cooling water to the plant on an emergency basis if some portion of the mitigation device should become inoperable during a natural disaster.
When the mitigation screens are in operation, larval fish samples will be collected weekly. The number of ichthyoplankters in the river _ 2 passing the plant will be estimated from samples collected at a transect upstream of the plant intake. Numbers impinged on the screens, surviving impingemenc on the screens, and en'. rained through the screens will be similarly estimated frca samples concoaitantly collected off the screens, from the return sluice, and from the intake channel, respectively, or at other appropriate locations.
Upon initial startup of the mitigation screens, the monitoring results are expected to provide the basis for " tuning" the screen operation (e.g., adjusting screen travel rates, screen washwater pressures, etc.).
794Gk
Plant Intake When larval fish are not present in signific.2nt numbers, the intake water will bypass the mitigation screens and flow to the plant intake pumping station via an intake channel. Conventional through-flow vertical traveling screens with 3/8-inch mesh are contained in the intake pumping station. Fish impingement counts will be made biweekly to determine the need to operate the mitigation screen device during periods other than when larval fish are present.
Entrainment of drift macroinvertebrate will be monitored by collecting monthly samples at transects in the intake channel and in the Holston River upstrear from the intake. The types of macroinvertebrates most susceptible to entrain-ment will be determined and macroinvertebrate loss due to the plant will be estimated. Zooplankton and phytoplankton will not be monitored. These communities do not constitute a major part of the food chain in free-flowing streams, and their loss will not result in an alteration of the indigenous fauna and flora of the Holston River.
784Ch