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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:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20151C0371988-03-28028 March 1988 Forwards Suppl to Re Plant Diesel Generators. Suppl Replaces Item 4, Tests on Diesel Generators & Clarifies Ltr Concerning Tests Required by Reg Guide 1.108 ML20150D5721988-03-0808 March 1988 Provides Summary of Utils Test Results & Calculations on Emergency Diesel Generators,Including Review of Design of Static Exciter & Voltage Regulator for Emergency Diesel Generators ML20196C1591988-02-0303 February 1988 Forwards Monthly Progress Rept P-C6177-5, Independent Analysis & Assessment, for Period Ending 880131 ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20236J6651987-07-24024 July 1987 Forwards Schedule for Five Specialists Assigned to Special Testing & Startup Activities for Plant.Total Time Comes to 303 Days,Close to Level of Effort Contained in Statement of Work ML20237J2141987-07-0202 July 1987 FOIA Request for Listed Documents Ref in NUREG-1150 & Related Contractor Repts ML20214J9761986-10-15015 October 1986 FOIA Request for Containment Event Trees for Listed Facilities,Technical Repts & Memoranda Re Interpretation & Quantification & Identification of FIN Numbers,Contractors & Investigators Involved in Creation/Analysis of Event Trees ML20214K0231986-10-15015 October 1986 FOIA Request for All Documentation Re Accident Sequence Evaluation Program Repts Re Listed Facilities in Preparation for NUREG-1150 ML20199E7311986-02-0606 February 1986 FOIA Request for Totals of NRC Fees Charged for 1985 Under 10CFR170 for Listed Facilities ML20132F5751985-08-13013 August 1985 FOIA Request for Power Plant Exam Results Summary Sheets for Listed Plants ML20134L5011985-06-19019 June 1985 FOIA Request for Operator Exam Results Summary Sheets for Listed Nuclear Plants ML20133C5961985-05-23023 May 1985 FOIA Request for Section 55.25 Exam Summary Sheets Prepared by Operator Licensing Branch for Operator Candidates & Monthly & Quarterly Repts on Senior Operator Performance on Exams ML20126E1901984-12-28028 December 1984 FOIA Request for Info Re Initial Operator Written Exam Results on Number of post-TMI-2 Plants.Info Provided in Did Pertain to Initial Exam Results.Table Listing Dates of Initial Licensing Encl ML20107K6231984-11-0101 November 1984 FOIA Request for Four Categories of Documents Re Results of Written Operator Exams at Listed Facilities,Including Dates of Exams & Number of Candidates Taking Exams ML20105C0271981-01-0909 January 1981 Forwards Evaluation of Glow Plug Igniter Concept for Use in Sequoyah Nuclear Plant, Per Request ML19344F1881980-08-18018 August 1980 Responds to Request for Comments Re Sequoyah Containment. Forwards Info Re Stringer & Skin Interaction.Concludes NRC Calculations Overestimated Beneficial Effect of Stringers ML19331B8281980-08-0404 August 1980 Forwards Hydrogen Problems in Sequoyah Containment. Encl Is Second Part of Rept on Ice Condenser Plant Containment Response to Hydrogen Production & Burning & Mitigation by Igniters ML19331C2231980-07-25025 July 1980 Forwards Critique Sequoyah Containment Analysis, in Response to NRC Request ML19330C2131980-07-25025 July 1980 Forwards Critique of Ames Analysis of Facility Containment. Detailed Finite Element Code Analysis Should Be Carried Out to Clarify Stress concentration.Full-scale Excastre Panel Should Be Pressurized to Failure ML19338E9851980-03-10010 March 1980 Discusses 800204-08 Essex Corp Human Engineering Evaluation of Control Room.Control Room Exhibited Design & Procedural Features Contradictory to Human Engineering Stds ML20064C5981978-10-0707 October 1978 Forwards Hydrology Engineering Summary Per Lg Hulman 780913 Request.Recommendations for Rev to SER Encl 1988-03-08
[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] |
Text
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Evaluation of the Glow Plug Igniter Concept for use in the Sequoyah Nuclear Plant I
Prepared for Mr. James Milhoan, P. E.
- l i Office of Policy Evaluation Nuclear Regulatory Commission Washington , D. C. 20555 i
Prepared by Roger A. Strehlow Consultant January 9, 1981 e , .i , Ab
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f Overall' Evaluation *
- In my opinion, a well designed and maintained glow plug igniter system which is energized only for testing or during an ,
event which has the potential of generating hydrogen is an l effective way to protect the Sequoyah nuclear plants from the i
i, possibility of breaching the containment vessel due-to the i Furthermore, it inadvertent combustion of accumulated hydrogen.
l 1s my opinion that the implementation of this glow plug igniter i technique will have no negative effects on overall safety in such I
a nuclear plant. I base this opinion on the following information f
- that was supplied to me 'by the Nuclear Regulatory Commission
- ,
l Tennessee Valley Authority, Sequoyah Nuclear Plant Core l
Degradation Program, Volume I, Hydrogen Study, i September 11, 1980
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News Release No.80-159, USNRC, September 11, 1980
' News Release No.80-163, USNRC, September 18, 1980 l Safety evaluation report related to the operation j Sequoyah Nuclear Plant, Units 1 and 2, Docket i No. 50-327 and 50-328, Tennessee Valley Authority, j NUREG-00ll, Supplement No. 3, September,1980 1
j Memorandum for: ACRS members , from: J. C. Mark, Subject l
Notes on hydrogen burn with igniters, December 4, 1980 l Memorandum to: ACRS members , from: H . Etherington , '
j Subject Memorandum P. G. Shemwon to ACRS members:
" Quantity of H 2 at TMI-2 and source ."
l
! Tennessee Valley Authority, Sequoyah Nuclear Plant Core l
Degradation Program, Volume 2, Report on the Safety i Evaluation of the Distributed Ignition System, December 15, 1980
- Tennessee Valley Authority, Sequoyah Nuclear Plant, Research
! Program on Hydrogen Combustion and Control, Quarterly
( Progress Report, December 15, 1980 l
Draf t copy of Supplement No. 4 to the Safety evaluation report by the Office of Nuclear Reactor Regulation, U. S . Nuclear Regulatory Commission in the matter of Tennessee Valley Authority Sequoyah Nuclear Plant Units 1 and 2, Docket No's. 50-327 and 50-328, undated.
Attendance at the ACRS subcommittee meeting held in Washington, D. C. on January 6, 1981.
A meeting with Mr. Tinkler and Mr. Butler of the NRC staf f on the morning of January 7,1981.
Other open literature references which helped me form my opinion will be referenced in the detailed supporting statement
- that follows. I also have opinions concerning the dynamics of a combustion explosion in a Sequoyah type containment and new research and data accumulation efforts which would be necessary to strengthen and quantify the justification for using glow plug igniters as the only hydrogen control technique. These will also
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be disucssed below.
4 Effectiveness of the Glow Plugs.
The Singleton Lab.,- Fenwal and LLNL tests have shown the glow
- plugs that are being considered for the Sequoyah plant to be very effective igniters down to 5% hydrogen even in the presence of 15% dry steam. Thus, in a real accident we now know that the igniters would initiate a partial burn at 5% H2 in the CV. Further-more, the ' Singleton lab tests show that in a small vessel even with 3.5% H2 present initially a five minute " burn" reduces the H2 concentration to about 0.1%. This is very encouraging because i it shows that a hot glow plug will act as an H2 scavenger even t
outside the flammability limit for upward propagation of about 4% H2 . Furthermore, sparks of the type that undoubtedly initiated the Three Mile Island burn are not effective at such a low hydrogen
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. concentration. '
It is important to note that glow-plug initiated burns will be much less dangerous t!.an spark initiated burns. This is because between 4-8% hydrogen in air burns with a very lazy upward propagating flame which ' spreads at a maximum half angle 'of about 20 degrees and extinguishes when it reaches the top of the vessel. Tnis means two things: 1) the pressure rise will be minimal for such a burn, and 2) the hot product gases will be confined to this cone-shaped volume and subsequently will spread .
along the ceiling. In other words, the flame will not contact and therefore not heat most equipment that is in the containment vessel. Also, if the rate of hydrogen generation were slow so that the fans produced a rather uniform hydrogen concentration, the burn would be almost continuous once the hydrogen content reached 4-5%.
On the other hand, a fast leak which caused a localized higher concentration of hydrogen would also not be dangerous when ignited by the glow plug. This is because glow plugs strategically placed above potential
- hydrogen sources would ignite a high hydrogen concentration pluna on contact and only a localized high temperature burn would occur. It is well documented .(Cubbage and )
Marshall,1972) that such a partial burn yields a pressure rise in
- a vessel which is proportional to the energy released by the localized burn (Joules) divided by the total volume of the vessel 3
(m ). Thus, a small localized burn cannot cause a r,eally large l
j pressure rise.
In my opinion, properly located and functioning glow plug igniters would reduce the probability of a burn lead,ing to a j t
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' transition to detonation to virtually zero. This is because the very weak flames produced by a 4-5% hydrogen burn cannot generate significant pressure waves or significant flow velocities ahead of the flame. This means that the mechanisms that lead to flame acceleration do not exist under these conditions. In other words, the weak 4-5% hydrogen flames will remain weak irrespective of the environment that they encounter.
Combustion dynamics in the Sequoyah containment vessel.
The Sequoyah containment contains three main compartments :
- 1) the upper compartment, 2) the lower compartment, and.3) the ice condenser. The upper and lower compartments both have a rather low length-to-diameter (L/D) ratio and therefore if they could be treated as independent vessels they would be capable of supporting only a simple over-pressure explosion. The containment at Three Mile Island was essentially of this type and that is what happened there when the hydrogen concentration reached about 8%.
In such a case, the flame propagates slowly enough such that the pressure is relatively uniform spatially in the vessel during the burn and simply rises with time (approximately as a cubic of time; see Bradley and Mitcheson, 1978 a, b). This is true even if there is some acceleration due to turbulence generation. Under these conditions, there are essentially no pressure waves generated.
Note that at TMI the transit time of a sound wave from top to I bottom to top is about 0.2 seconds and the burn took about 10 seconds.
Unfortunately, in the Sequoyah configuration the upper and l lower compartments are not independent but are connected by the l
- ' ice condenser. In my opinion, this is a very dangerous configu-a ration because it would generate pressure waves which could possibly lead to local over pressures that could breach the 4 containment. This is because the ice condenser contains hundreds i of tubes (the spaces between the baskets) which have a very lar'ge L/D and which could cause significant flame acceleration and possibly even transition to detonation. This mechanism has been
! adequately documented by Urtiew et al (1965, 1967) and could occur after primary ignition at or above 8% in either the lower or upper j
! compartment. The sequence, without detonation, is as follows :
ignition in one compartment causes a slow pressure rise and starts
! a flow through the condenser, pressurizing the second compartment.
I j The flame then gets into the ice condenser at some location and i
j accelerates in this turbulent flow causing large turbulent jets to l enter the second compartment. Once the flame reaches the second l
compartment, it is already pre-pressurized and the burning velocity is now so large that combustion in this compartment produces pressures that are up to a factor of 2-4 above the calculated
! maximum adiabatic constant volume pressure (Heinrich,1974) .
I i There is another more recently discovered combustion dynamics i possibility. Knystantas et al (1979) have shown that large scale eddy folding of hot combustion products into an already turbulent l jet of reactants can produce shockless initiation of detonation.
[ Here the nachanism is that radicals in the product gases trigger i
! combuscle.1 reactions in the mixing volume and as the system explodes the pressure increase augments the combustion process.
This coupled augmentation eventually culminates in a detonation l
l wa,ve. For hydrocarbon-air mixtures, the critical eddy size is i
(
i large,' about three meters in diameter. Note that at the exit j
of the ice condensus, conditions would be right for the formation of such a large mixing region. The required eddy size for hydrogen-air is not known but it would probably be smaller than i
the critical size for a hydrocarbon-air mixture.
l Thus, in my opinion, the combustion dynamics of an explosion
! in which a continuous flame is able to propagate (i.e., in a i mixture containing greater than 8% H 2 ) is a very dangerous situ-i l ation and would have the potential to breach the containment l vessel. We know that glow plugs have been shown to yield partial i
- burns when the flame is lazy and not dangerous. This, coupled I
with the vulnerability of the facility to a dynamic combustion explosion, is one more point in favor of using glow plug igniters to protect the containment vessel from the adverse consequences i
l of an accidental spark-ignited burn, i
l 4 Research Needs.
Glow plug testing should be continued. Specifically, I agree i
with the LLNL recommendations for further work that was presented i
! at the ACRS subcommittee meeting of January 6,1981. I would also
! like to see some continuous burn tests at concentration less than
- 4% to determine how rapidly a glow plug will scavenge hydrogen at
- these low concentrations. In these tests, the effect of f an-induced i
flow across the plug should also be investigated.
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Even though I feel that the glow plugs will virtually elimi-nate the possibility of detonation in the containment vessel, I still feel that some work on detonation limits should be performed.
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I.do not believe the 18% figure that is in the reports. I feel that the limit 15 much lower, possibly 12%. At any rate, this uncertainty can be relatively easily answered by a few rather simple tests that should be performed.
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References Bradley, D. and Mitcheson, A. (1978a) , Comb and Flame 32, --
pp. 221-236 Bradley, D. and Mitcheson, A. (1978b) , Comb and Flame 32, pp. 237-255 Cubbage, P. A. and Marshall, M. R. (1972), " Pressures generated l in combustion chambers by the ignition of air gas mixtures",
! I. Chem E. Symposium Series #33, Inst. of Chemical Engineers,.
! London, pp. 24-31.
Heinrich, H. J. (3974), " Sum Ablanf von Gas explosionen in mit Rohleitungen verbundenen Behadtern", BAM Berichte #28, Berlin (August 1974).
Knystantas, R.; Lee, J. H.; Guirao, C.; Freuklach, M.; and Wagner, H. G., " Direct Initiation of detonation by a hot turbulent gas jet", 17th Symposium (International) on i Combustion, The Combustion Institute , Pittsburgh, Pa. ,
(pages unknown).
Utriew, P.A'. and Oppenheim, A. K. (1967), " Detonation Initiation by Shock Merging",11th Symposium (International) on Combustion, The Combustion Institute, Pittsburgh, Pa. ,
pp. 665-676.
i Utriew, P. A., Laderman, A. J. and Oppenheim, A. K. (1965),
" Dynamics of the Generation of Pressure Waves by Accelerating Flames",10th Symposium (International) on Combustion, The Combustion Institute, Pittsburgh, Pa. , pp. 797-804 4
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