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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 CHATTANOOGA TENNESSEE 374ot SN 157B Lookout Place 08T 201988 U.S. Nuclear Regulatory Commission !
ATTN Document Control Desk ,
Washington, D.C. 20555 Centlemen In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 l SEQUOYAH NUCLEAR ELANT (SQN) - NRC INSPECTION REPORT NOS. 50-327/87-56 AND
$0-328/87 RESPONSE TO EVALUATION OF NOTICE OF VIOLATION NOS. 50-327, 328/87-56-02 Enclosed is IVA's response to S. D. Richardson's August 31, 1988 letter to S. A. White that transmitted NRC's evaluation of TVA's resps m to the subject notice of violation.
TVA initially responded to the notice of violation by letter d. ed November 6, 1987. TVA provided additional information in a letter dated May 13, 1988. Subsequent NRC review and evaluation of these responses were '
- forwarded to TVA on August 31, 1988. After discussion with Office of Special Projects and Region II inspectors and management, IVA understands that NRC may j noc have fully understood pertinent information regarding this issue.
Therefore, Jn response to an NRC verbal request for more detailed information, TVA is transmitting a history of laundry and shower drain processing, along ,
with an additional response to NRC regarding the subject violation in the enclosure to this letter. TVA's evaluation of NRC's August 31, 1980 i transmittat does not indicate a violation of 10 CFR 50.59 has occurred. In consideration of the enclosed response, TVA respectfully requests NRC l withdrawal of this violation. The change in the due date for this rene sti 1 i
was discussed with F. R. McCoy, of NRC, and J. T. LaPoint, of TVA, n '- !
seatch 30, 19881 and 4.n extension to November 1, 1988, was latsr - id
,. - Brady, of your staff. l I t' 'c . , to any questions, please telephone M. A. Cooper at (615) 870-6549. !
Very truly yours,
. TENNESSEE VALLEY AUTHORITY 0010250437 891020 nu .
/ )
4 PDR ADOCK 05000327 R Gri r j 0 PNU- Nuclea'pey,Ma r Licensing and i
Regulatory Affairs l
i Enclosure, ect See page 2 f#6i a An Equal Opportunity Employer
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U.S. Nuclear Regulatory Coaunission g '
cc (Enclosures): :
Ms. S. C. d!ack Assistant Director '
for Projects TVA Projects Division i L.S. Nuclear Regulatory Commission -
- One White Filnt, Nerth ,
, 11555 Rockville Pike :
i Rockville, Maryland 2085* ;
Mr. F. R. McCoy, Assistant Director
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) .or Inspection Programs :
TVA Projects Divisien :
4 U.S. Nuclear Regulat'ry Commission ;
i- Region II i 101 Marietta Street, NW, suite 2900 t 1 Atlanta, Georgia 30323 i i i l Sequoyah R2sident Inspecto' !
Sequoyah Nuclear Pls.it !
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Soddy Daisy, Tennessee 37379 j t
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ENCLOSURE 1 Violation 50-327, 328/87-56-02 "Restatement of Violation 10 CFR 50.59 states that the holder of a license authorizing operation of a utilization facility may make changes in the facility as described in the safety analysis report, without prior Commission approval, unless this proposed change involves a change in the Technical Specifications incorporated in the license or an unreviewed safety question. The licensee should maintain records of changes in the facility which shall include a written safety evaluation which provides the bases for the determination that the change does not involve an unreviewed safety question.
Final Safety Analysis Report (FSAR), Chapter 11.2 states that the laundry and hot shower drain tank is normally sampled and discharged as an effluent, with the provision for processing the liquid through the condensate demineralizer waste evaporator (CDWE) if the sample result was above the discharge limit.
Contrary to the ubove, in May 1987, the licensee failed to perform an adequate safety evaluation for a change in the laundry and hot shower waste water process which directed all the waste water to the CDWE causing an increase in the volume and conceatration of contaminants into the CDWE."
History of Laundry and Shower Drain Processing As a result of recent discussions with Of fice of Special Projects and Region II inspectors and management, it appears that NRC may not have a fully accurate understanding of all facts surrounding this issue. Therefore, before responding specifically to NRC's August 31, 1988 letter, a brief discussion of the history and background leading to the subject issue is provided.
Since initial operation, releasing or processing of the laundry and hot shower d:ains hcs been based on various considerations such as activity levels of these wastes, river flow rate and temperature, activity leve ls of recent releases, tank needs for the entire facility operation, future planned releases, plant decontamination efforts, and 10 CFR 50, Appendix I, "as low as i
reasonable achievable" (ALARA) considerations. SQN had always used Turco as a laundry detergent for decontamination purposes in the laundry. In addition.
Turco had been used for decontamination of areas.
Dafore this particular event in 1987, SQN was andergoing a large-scale facility decontamination effort in preparation for return to power operation.
There was a large volume of laundry that required cleaning, and Turco was beinL u ed for area decontamination es well. Because of the decontamination effot , low flow rates in the river, and ALARA considerations, the laundry and hot shower tanks wnre being transferred to tne CDWE for processing.
The subject event occurred while attempting to solidify a specific batch of CDWE bottoms for packing and shipping offsite. In preparation for j solidification, a representative test specimen was taken of the specific batch and a solidification test was performed, in compliance with technical 4
I i
specifications (TSs) and the approved pr cess control program (PCP). The solidification test yielded acceptable re.sults with no adverse reaction. It should be noted that slight exothermic reactions always occur because of i inherent chemical reactions during solidification. After the test specimen was verified as acceptable, the batch was pumped into the liner and the solidification chemicals were iatroduced into the liner in accordance with the i PCP. The liner was filled to a precalculated level that would allow the addition of chemicals and slight expansion with no voids in the liner.
Disposal site criteria require the container to be 95-percent full.
After the greater than anticipated exothermic reaction occurred, the solidification process was halted in accordance with TSs and the PCP. The vendor vas requested to perform an analysis of the waste stream and solidification materials to determine what caused the reaction. This analysis revealed that Turco ar.d the vendor solidification agents were highly reactive. It was also determined that reactions could be i concentration-dependent and volume-dependent, i.e., excessively reactive (only i under certain conditions). TVA stopped the use of Turco and subsequently i learned that other utilities had experienced similar difficulties with Turco.
The potential for a similar recurrence of this type of event (resulting f rom chemicals introduced into waste streams) is minimal. Only a small number of chemicals are used in the plant that roight be introduced into waste streams, with the only significant quantities being in cleaning activities. Those currently used onsite have an existing experience base and have been (valuated as acceptable. Additional actions have been taken, as described in TVA's response of May 13, 1988, to ensure any new chemicals used in the picat that could be introduced into ;he waste streams will be evaluated for chemical reactions with vendor solidification materials. In compliance with TSs, a -
test specimen is taken before batch solidification. ,
i In summary, TVA's actions associated with this event did not constitute a ;
change in the facility or operation as described in the FSAR. TVA's actions j with regard to processing were taken after consideration of a variety of :
pertinent factors; neither past experience nor results of test specimens had i predicted the event, and prudent actions were taken in response to the event, r T7A's actions associated with the event were conducted in accordance with '
SQN's FSAR TSs and PCP. i l Licensee Comment TVA would like to resolve the possibte confucion resulting from two separate issues apparently being viewed as the same issue insofar as cause and effect.
The first issue involves the question of whether a change was made to the facility as described in the safety analysis report that required an unreviewed safety question determination (USQD) in accordance with 10 CFR 50.59. The second issue involves the cause of an exathermic reaction that occurred during the solidification of waste that resulted in swelling of the material outside the confines of its shipping container; the material subsequently had to be chipped away to seal the shipping container. TVA complied with TS limiting condition for operation (LCO) 3.11.3, which has specific provisions for unexpected occurrences of defectively processed or defectively packaged solid radioactive wastes, t
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It must be understood that the first issue (the cited change m.id not conducting a 10 CFR 56.59 review) had ne reintion to and did not cause the i second issue (exothermic reaction). The cited change involves more frequent processing of laundry and hot shower drains; this was not precluded by.the SQN FSAR. More frequent processing did not cause the exothermic reaction to occur. The reaction resulted from a concentration of a laundry detergent in CDWE bottoms that reacted chemically with the vendor's solidification agents i to cause the swelling during the solidification process. TVA did_not have i reason to expect this reaction. Any processing of laundry drains with this i i detergent, whether based on sample activity or not, could have resulted in a i
! chemical reaction. However, this is not a 10 CFR 50.59 review issue. A change was not made to the facility or operating procedures. A particular 1
- brand of detergent is not specified in the FSAR, the FSAR low-sudsing requirement was always met, and the detergent had been used previously without I adverse reaction. In addition, a 10 CFR 50.59 review of more frequent !
processing would not have identified a potential exothermic reaction. This !
clarification is necessary to put the violation cited in proper perspective
] for subsequent evaluation and discussion of validity.
- i l TVA Specific Response to NRC Letter Dated August 31. 1988 The following is TVA's response to NRC's specific reasons cited in the August 31, 1988 letter for determining the violation occurred as stated and ,
i will further explain why TVA finds that the information provided does not constitute a basis for a violation of 10 CFR 50.59. l
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1 Ec !
"FSAR Section 11.2 toes much further than merely allowing direct dischargo :
from the laundry and hot shower tanks if sample results are below acceptable i limits. FSAR Section 11.2.3.1 and 11.2.4 both state that the water is i i processed only if the activity cencentration is too high for direct discharge." i i l i TVA
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The FSAR does not state that the water is processed only if activity I concentration is too high for direct discharge. The cited FSAR section ;
states, "If the activity concentration is too high for direct discharge, the j waste may be pumped tn the floor drain collection tank for further j processing," and "normally no treatment is required for removal of j 4
radioactivity." .Sischarge limits for effluents are prescribed and regulated !
l by 10 CFR as are limits for radiation exposure to workers. A licensee may '
impose more restrictive limits than prescribed in 10 CFR. Changes in those i administrative limits, up to those prescribec by 10 CFR or other NRC {
q regulations, are at the discretion of the licensee and are not prohibited by a the FSAR. Reducing total activity in liquid effluents is supported by the :
! 10 CFR 50, Appendix I. ALARA concept.
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"FSAR Section 11.2.4 statcs that normally no treatment ic required for removal
- of radioactivity. While not precluding additional processing, the FSAR l clearly indicates that such processing only occurs if the activity I concentration in the tanks is above discharge limits, otherwise it is directly dischar8ed. Therefore, processing would only be int'requently required."
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TVA 1
The FSAR states that water does not normally require processing. The FSAR l doet not clearly indicate that processing only occurs if activity levels are above discharge limits as previously discussed. The FSAR is written ir.
permissive, not mandatory or restrictive, terms and allows processing of laundry and het shower drains more frequently than required (but certainly no 1ess than required). Therefore, it is speculative to presume processing would always be infrequent; the FSAR does not reference the term infrequent. The FSAR was written to reflect the licensee's ability to operate within the legal l constraints of 10 CFR. The FSAR clearly provides lati*ude for processing
( (beyond that required by 10 CFR) as deemed appropriate.
I E I
"In May 1987, the licensee changed the process so that all of the wc.ste would be processed through thn CDWE prior to being sampled for re? ease. This was a change from how the licensee had handled this waste up to that time and was a change from the FSAR description of the disposition of this waste."
l TVA Upon further investigation, TVA has verified that SQN had been intermittently processing laundry and hot shower drains through the CDWE for an extended period of time before the event occurred. Such processing was based on evaluation of va ious factors such as activity levels of wastes, river flow and temperature, activity levels of recent releases, tank needs for the entire facility operation, and ALARA considerations. TVA did net change the process of handling waste water, the proceCurch for processing the waste, the waste water processing system, or the operadon of the system. The more frequent processing was conservative in that reduction in the overall activity in releases to the environment was achieved. The statement, "Normally no treatment is required for removal of radioactivity," conveys that, at a minimum, discharges will be processed to meet li:aits with the obvious latitude '
to process more waste. This latitude is clearly provided in the FSAR by I referen:e to sections 11.2.3.1 and 11.2.4, and this change i not subject to 10 CFR 50.59. Moreover, the language of the FSAR paragraphs should be considered with the overall context of the FSAR, Chapter 11.2 "Liquid Waste Systems." j Far ex.smple, FSAR, Subsection 11.2.1, "Design Objectives." ctates in part, )
"The Liquid Waste Processing Sy. item is designed to receive, segregate, process, recycle and disebcrge liquid wastes. ne system design considers potential petrontw! expcura and assures that quantities of radioactive i
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l releases to the environment are as low as practicable" (emphasis added}.
I FSAR, Section 11.2.4, "Operating Procedores " states in part, "All equipment installed to reduce radioactive effluents to the minimum practicable level is maintained in good operating order and will be operated to the maximum extent practicable. In order to acsure that these conditions are met. administrative controls are exercised on overall operation of the system . . . " (emphasis added). NRC agreed with TVA's course of action as evidenced in their l statement, "The NRC does not disagree with the goal of the change, to reduce concentration of radioactive material in effluents."
l NRC "The prccess followed by the licensee in making the change did not include a review of the change under 10 CFR 50.59, as was required since the change resulted in operation different f rom that described in the FSAR.
10 CFR 50.59(a)(2)(ii) states that a proposed change, test, or experiment shall be deemed to involve an unreviewed safety question if a possi*sility for an accident or ma function of a different type than any evaluated previously 1
in the cafety anal.wic report may be created."
E As discussed in the previous paragraph, TVA did not make a change to th(
l facility or procedures as described in the FSAR or conduct tests or experiments not described in the FSAR. TVA considers a review under 10 CFR 50.59 inappropriate. A primary purpose of 10 CFR 50.59. as related to this type of issue, is to ensure that the licensee does not make changes to the facility that could invalidate the bases on which NRC issued the license for operation of the facility. Even if one assumed the FSAR wording Indicat7o processing of laundry and shower drains would be infrequent, it is still
, unclear how a presumption of infrequent processing of drains had any relevance or hearing on NRC issuance of the SQN licenses. It is also unclear how more frequent processing could in any way invalidate the bases of the license; therefore, it veuld be reasonable to presume a 10 CFR 50.59 evaluation would not be required. Had the design or installation of facilities to process ,
wastes been altered--e.g. , changes to the CDWE--that type of change would have '
been subject to 10 C7R 50.39 review. NRC issues regarding design and i operation of the SQN CDWE were independently resolved for restart of SQN '
anit 2. Requiritig a 10 CFR 50.59 review for "changes" relative to the FSAR at this threshold could result in a significant increase in 10 CFR 50.59 reviews, which are not required to support the underlying purpose of 10 CFR 59.59 and would only serve to dilute the effectiveness of the licensee's 10 CFR 50.59 review program, hy t
"Since tho licensee's change to ..rocessing the laundry waste stream ,
continuously resulted in the oserflow of waste solidification liners and !
subsequent exposure of personnel, a malfunction of a different type than any '
evaluated previously, then this change involved an unreviewed safety question and should have been evaluated by the licensee."
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TVA ,
Intermittent processing did not result in the overflow of waste solidification liners as previously discussed. Tnis event resulted from concentration of laundry detergent (Turco 4324NP) in CDWE bottoms that was especially reactive with vendor solidification agents. The only FSAR reference to detergent with regard to processing laundry and hot shower drains was to state that low-sudsing cleaning agents would be used. Turco 4324NP is a low-sudsing detergent. The event was not a result of a change in the facility as described in the FSAR; therefore, discussion of evaluation in accordance with 10 CFR 50.59 is inappropriate. If TVA had performed a 10 CFR 50.59 screening review for more frequent processing, the screening review would have indicated there was no change as described in the FSARt therefore, no 10 CFR 50.59 review would have been required. Even if a 10 CFR 50.59 review had been performed for more frequent processing, the chemical reaction associated with the detergent and vendor solidification agents would not have been identified. Furthermore. TVA had used the Turco detergent regularly and had never experienced a reaction that prevented the solidification criteria from -
being met. Based on that experience, TVA had no reason to believe that an event of this type would occur.
The TSs have provisicns for occurrences of unknown type during the solidification process. LCO 3.11.3 requires that shipments of defectively processed or defectively packaged solid radioactive waste be suspended when provisions of the process control progran are not satisfied. Surveillance requirement TS 4.11.3.1.a is satisfied by verifying the tolidification of at least one representative test specimen trom at least every 10th batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporstor bottoms). This surveillar.ce requirement was complied with during this event because processing was suspended immediately. TVA considers all actions that took place during the episode were in accordance with SQN's PCP. TVA has addressed the specific event issue and now requires that chemicals that can come into contact with vendor solidification material be tested by the vendor for chemical compatibility before being used. TVA's actions in this area were addressed in a letter to NRC dated thy 13, 1988.
NRC I
"FSAR Section 11.2.1 does state that the design of the liquid waste processing system considers potential personnel exposures. The effect of processing the laundry waste was inconsistent with this design objective in that when the licensee attempted to solidify the CDWE bottoms containing high concentrations of laundry detergents, the liner content overflowed due to chemical reaction with the solidification agent. The overflow then hardened and personnel had to chip away the excess material, which measured up to 3 R/ hour, so that the lid could be placed on the liner. The change to the rou ine method of processing the laundry waste should have received a review under 10 CFR 50.59, and if found appropriate, the change could then have been implemented." ;
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_7 TVA ,
The more frequent processing of laundry waste had no effect on the design or design intent of the liquid waste processing system except in a positive sense to reduce total activity of liquid effluents. Changes in frequency of processing did not cause the cited event. As detailed previously, a review under 10 CFR 50.59 is inappropriate and would not have identified this event as a consequence. In the overall objective of ensuring an incident of this type does not recur, TVA has taken steps as defined in tbe May 13, 1988 letter to NRC.
NRC "The NRC agrees that licensees should make efforts to reduce the activity in their effluents; however, applicable requirements have to be followed when changes are made. The licensee acknowledges that they made a change to their process. The licencee's statement that the change was not inconsistent with the FSAR is valid when considering the oserall goal of reducing waste in effluents. Nevertheless, the FSAR clearly states that the waste stream is not normally processed, and the change caused all of the waste to be processed through the CDWE. This change was a significant change to a system described in the FSAR, and the edverse chemical reaction which occurred during waste solidification resulted in unnecessary radiction dose to radwaste operators."
TVA As stated previously. TVA does not acknowledge that a change was made to the process. No change was made in a system as described by the FSAR. The FSAR does nnt state that the waste stream is not normally processed; the FSAR (section 11.2.4) states, "Normally no treatment is required for removal of radioactivity." More frequent processing did not cause the adverse chemical reaction. No significant change to the aystem occurred. While certainly undesirable, radiation dose to radwaste operators resulting from the exothermic reaction of the detergent and vendor's solidification agent was well within limits preacribed by TVA and NRC. TVA has taken actions detailed in the May 13, 1988 letter to address the possibility for recurrence of this i
type of problem.
NRC "This staff position is consistent with the guidance provided to the licensee in IE Circular No. 80-18: 10 CFR 50.59, Safety Evaluations for Changes to Radioactive Waste Treatment Systems which states that for any change in a facility radioactive vaste system as described in the FSAR, a safety evaluation is required in accordance with 10 CFR 50.59."
TVA l
Inspection and Enforcement Circular No. 80-18 primarily addresses how to i
perform safety evaluations when changes in the derign and/or operation are made to radwaste treatment systems, not whether a safety evaluatian is required. There were no changes made to the physical system or to the l operational aspects of the system; therefore, guidance provided by this I circular is not germane to this discussion.
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- NRC Conclusion -
3 r "For the above reasons, the NRC staff concludes that the violation occutred as stated." '
W.$
In conclusion, the actions taken by WA with regard to processing laundry and [
hot shower drains were conservative and permissiblet did not constitute a '
I change in the facility or procedures as described in the FSAR; and, accordingly, did not require a review under 10 CFR 50.59. The exothermic !
reaction leading to the discussed event did not result from the more frequent !
i processing of the laundry and hot shower drains. Actions have been taken to i 1
preclude this type of event from recurring. TVA concludes that no violation '
j of 10 CFR 50.59 occurred as associated with these issues.
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