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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] |
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3D - 33 5' R & D ASSOCIATES Post Office Box 9695 lh Marina del Rey, California 90291 4 August 1980 Nuclear Regulatory Commission 1717 H Street, N.W.
Washington, D. C. 20555 Attention: Commissioner Victor Gilinsky
Dear Victor:
Enclosed is the second part of our report on ice condenser plant containment response to hydrogen production and burning and mitigation by igniters. If you have any ques-tions or comments, please call. We expect to see you and John Austin on Friday.
Best regards
'i Harmon W. Hubbard HWH/dl
Enclosure:
" Hydrogen Problems in Sequoyah Containment,"
August 1980.
1 l
, 8008130323 ,
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.. 6 - -
HYDROGEN PROBLEMS IN SEQUOYkN CONTAINMENT INTRODUCTION ,
This letter report completes the RDA response to a request from the Nuclear Regulatory Cohc.ission to critique the ultimate strength analysis of the'Sequoyah containment. This second report deals with the last two tasks of the work statement.
- 1. HGw would the an& lyses and results be altered if the stresses are caused by ignition / detonation of 300-600 Kg of hydrogen distributed uniformly and nonuniformly in the containment?
- 2. To what extenc can distributed ignition sources mitigate the effects of hydrogen?
A preliminary discussion of these topics was attended by Commissioner Gilinsky and Dr. John Austin at RDA on 18 July 1980.
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RESULTS
- 1. a) 300 kg of H2 gas mixed uniformly with the air and steam (if less than 40 percent steam) in the Sequoyah -
containment volume following an accident would be completely combustible if ignited (see Figure 1).
This complete co'bustion m could occur so rapidly as to exceed the capacity of the available heat removal proepsses, and could produce a pressure as high as 5.5 atmospheres, thus rupturing the containment (see Table 2). The combustion of 600 kg of H2 * "1d f course have more severe consequences.
b) A nonuniform distribution of 300 kg of H 2
present in the containment would consist of parcels of gas richer in H than the uniform distribution. If these 2
separated parcels formed while the blowers were operating, they would probably be mixed, combustible and perhaps detonable. If they were all detonable and all ignited, the damage to the containment would be worse than that due to ignition of a uniform mixture. If the gas parcels were not detonable, the pressure upon combustion wculd probably be at least as high as the uniform distribution. Under,some circumstances, it would be possible to collect pockets of gas too rich in H to burn. As the outer edges 2
- of such pockets mix with air, partially combustible mixtures would form.. The.results of igniting such a distribution would clearly depend on the sires of the parcels and the timing.
It should be noted that harmless mixtures of H 2
, airabd
. steam may become highly combustible or detonable as steam is condensed out (see Appendix B).
Thus one mechanism employed for removing heat from the containment also removes the combustion inhibitor from the containment.
2 O
a
- 2. If the rate of hydrogen formation is sufficiently low, and the mixing of H is complete and rapid so tnat all -
2 the gas in the containment gradually increases in H 2 .
- concentration, then the presence of enough igniters could prevent overpressurizing the containment. This would be accomplished by releasing the heat of combustion at low concentrations over a long enough period of time to be handled by the heat removal equipment. However, if the 2r reaction rate is high relative to heat removal processes, then igniters might only delay containment failure.
Table 3 shows that a 1 percent per minute Zr re' action rate, accompanied by the burning of hydrogen at its rate of
, formation, would match the steady-state heat removal capacity of the RHR equipment.
j If the H is not thoroughly mixed, then there is a 2
! possibility of igniting a detonable pocket of gas with an l igniter. If left to its natural end, such an H -rich pocket 2
could disperse below the detonation limit- (420 percent H ) 2 when its ignition would cause less of a problem.
Since the possible rates of generation of H f 11 wiU9 2
an accident and the rate, place, and degree of mixing with
, air are highly uncertain, the use of igniters can only be an uncertain means of pressure control. Improper use might be detrimental rather than helpful. On the other hand, if it is assnted that there are many unavoidable igr.ition sources in the containment, it is certainly true that control of the time and place of ignition is preferable to chance. In this sense the use of igniters seems beneficial.
I COMMENT It is our opinion that the uncertainties in H2 generation ,
and mixing a,re so dependent on hardware details and scenarios that they are unlikely to be greatly reduced by further work.
For this reason we believe-it may be a better use of resources to explore thoroughly the feasibility of using an inert atmos-phere in the containment, so as to avoid the hydrogen burning problem. ,
. 3 i
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~
s 100% air 300 kg -H 1000F saturated steam 2g i 600 kg H2 836 kg H2 \N '
150 F steam
\ x
\ ,200 0F steam Assumed detonation limit
\E -
w Flammability \
NNNNN N &
\
20% air
's /
100% H 2 3 # 100%
steam Limits of flammability and detonation based on Shapiro and Moffette WAPD-SC-545, as reproduced in WASH 1400.
Figure 1. Uniform mixtures in the Sequoyah containment vessel. l l
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TABLE 1. INPUT DATA FOR SEQUC/AH PLANT
- 1. Free volume of containment vesse1I ") 3.2 x 104m3 -
Wefght of contained air at 27'C,1 atm. 3.7 x 104 kg Gram moles of air 1.3 x 10 6 Gram moles of oxygen .
2.7 x 10 5
- 2. Weight of zirconium in core (b) 1.9 x 104 kg Gram moles of zirconium 2.1 x 10 5
- 3. Yield of 100% 71rconium-water reaction Weight of hydrogen 836 kg, Gram moles of hydrogen 4.2 x 10 5 Heat of reaction (c) Zr + H 2O
, 1.1 x 10 II joules Heat of H 2 burn (d) (to form liquid H O) 1.2 x 10 ll joules '
2 Total heat of reactirsn + burn 2.3 x 10 Il joules
- 4. . Molar quantities and partial air pressure ,
of saturated steam in containment l At 100*F (38'C) vapor = 8.1 x 104 moles = 0.06 atm.
150*F(66*C) = 5.9 x 105moles = 0.25 atm. I 200*F(93*C) = 8.4 x 105moles = 0.78 atm.
NOTES:
(a) Sequoyah Nuclear Plant, Preliminary Safety Analysis Report (PSAR),
Table 5.2-1 gives the total containment active volume as 1,142,000 ft3 ,
comprised of 730,000 in the upper compartment, 125,000 in the ice compartment, and 287,000 in the lower compartment.
(b) ~ Sequoyah PSAR, Tabel 1.3-1, gives the clad weight as 41,993 lb.
(c) G. W. Keilholtz, ORNL-NSIC-120, Annotated Bibliography of Hydrogen Considerations in Light-Water Power Reactors, Feb.1976, Table 1 Heat of Reaction = 122 to 137 kcal/ mole Zr.
(d) Lewis and Von Elbe,
- p. 685, 68.3 kcal/ mole H20.
5 I
- - . - y.-.-.- .- , .
TMM 2
- H 2 Quantity 300 kg 600 kg 836 kg .
- 1. Percent Zr Reaction -36% 72%
1Q0%
- 2. Id es H2 ~
1.5x10 5 3.10 5
4.2x10 5
3.
Partial Pressure 9 300'k (atmospheres) 0.12 0.23
' H 0.32
- 4. Molar Ratio h, Uniform Distribtion 0.11 0.23 0.32
- 5. Detonatable Mixture, no s(team presentD) or Combustibk (C)"
C D D
- 6. H2 Concentration Multiplier Required relative to uniform mixture a a) to reach detonation regime 2.0 1.0 1.0 b) to reach stoichiometric ratio of 0.42
- 1 for H2 : air 3.8 1.8 1.3
- 7. Steam Vapor Pressure Required:b a) to prevent detonation of unifonn mixture
. 0 0.1 atm 0.4 atm b) to prevent combustion of unifonn mixture 0.9 atm 2.0 atm 2.3 atm
- 8. Energy Release in 100% Combustion, Joules (liquid water product) 4.3x10 10 8.6x10 10 1.2x10 11 9.
Final Absolute Pressure in Adiabatic Combustion (Initial Air Partial Pressure 1 atm, Initial Temperature 300*k)c i
"a ) No steam,100% combustion 5.5 atm 10.0 13.3 atm b) No steam, 50% ccmbustion -
3.3 5.8 7.3 c) Steam 9 190*F, 50% combustion j 4.1 6.5 8.3 NOTES:. [
t t
(a) Approximate, based _ on regimes outlined in Figure 1. '
(b)
Approximate, based on regimes outlined in Figure 1, plus molar ccncen-trations of saturated steam c: a function of pressure. !
(c) t Assuming p'roducts a constant-volume reaction' of combustion behave as ideal gases, and assumin i
t 6
t
es .
TABLE 3. HEATING'ANO COOLING RATES I SEQUOYAH CONTAINMENT Time when Fission Product Heat (Cumulative) Equals Total ,
Heat of Reaction 3000 see Rate of Heating at the 1% per min Zr Reaction Rate Zr Reaction 18.0 MW H2 Burning 20.0 Total 38.0 MW Rate of Fission Product Heating at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (when ice has been melted in DBA) 27 MW Steady-state, Cooling Capacity of the 2 RHR Heat Exchangers 67 MW Net Margin of Cooling Capacity (Beyond Chemical Reactions 01%/ min and Fission Product Heating) 2 MW NOTES:
(a) Sequoyah PSAR, Table Q.3-2 cites 2 heat exchangers, each having a capacity of 1.15 x 10o BTU /h at specified conditions.
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APPENDIX A LITERATURE SEARCH ON EXTENT OF HYDROGEN
- 1 BURNING AND FLAMMABILITY LIMITS FOR MIXTURES OF H , AIR, AND STEAM 2 l l
In considering the effects of 300 kg to 600 kg H 2 in the Sequoyah containment vessel, questions of lean mixture flamm-ability' limits and the extent of combustion are important.
The 1976 litkrature survey by Keilholtz (1) provided citations for most of the sources used in this brief study, and provided much of the available data on flammability and extent of ~
l combustion.
EXTENT OF COMBUSTION .
Keilholtz states that combustion of 100 percent of the hydrogen will not occur until the hydrogen comprises about 10 vol percent of the H -air mixture. A partial combustion 2
, data point of 50 percent combustion is quotea for a 5.6 vol percent H 2 mixture in air. This point is attributed to Shapiro and Moffette (2), a reference that we were unable to obtain in the available time. However, Furno, et al. (8) indicate about 90 percent combustion for an initial mixture of 8.5 percent H as compared with 5-10 percent combustion
' 2 for mixtures of.6.9-7.4 percent H . If 300 kg H w'#8 2 2 uniformly distributed throughout the active volume of the Sequoyah Unit 1 containment vessel, it would constitute a 10 vol percent mixture with air (neglecting steam), and hence could burn completely.
FLAMMABILITY LIMIT i The lean mixture threshold of flammability is given.by Keilholtz as 4.1 vol percent H in air bu.t at this concentra-2 tion, Egerto,n (3) as well as Keilholtz point out'that~the flame front is not coherent, and flame propagation is upward only.
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Downward propagation begins with a hydrogen concentration of about 9 vol percent (1), (3). Drell and Belles (4) state
~
that a 9 percent mixture will burn completely (a point'to be >
compared with the Keilholtz 10 percent mixture for 100 percent combustion). Even the lean mixture non-coherent flames are postulated to burn a mixture that is richer than the original mixture, because the high diffusion rate of H2 permits access of additional H to the flame (4). The diffusion rate of H 2 2
is also important to the dispersal of segregated pockets of hydrogen, and will be discussed later.
STEAM DILUTION The effects of dilution by steam are potentially important.
Drell and Belles (4) state that inert diluents have scarcely any effect on the lean-mixture limit of flammability, where 300-600 kg of H in Sequoyah would be, if uniformly distri-2 buted. They claim water vapor has effects similar to CO 2'
and they show data of Coward and Jones (5) (which we were unable to obtain) such that only after more than half the mixture is CO d es the fraction of H required for flamm-2 2 ability begin to increase. These findings are consistent with the ternary mixture chart of Shapiro and Moffette for
, H2, air, and steam, wherein the lean mixture flammability limit is at a nearly constant H fraction as the steam content 2
increases from zero to about 50 vol percent.
DETONATION Shapiro and Moffette indicate a triangular shaped detona-tion regime in their ternary mixture chart, a regime bounded
, approximately by a 19 vol percent H 2 line at the lean mixt 6re boundary and a 45 vol percent air line at the rich mixture '
boundary. Although the original reference was not available to us, it appears that the authors constructed the detonation l
regime by extrapolating from data on dry mixtures of H 2 and A-2 l .
I
_, m._ ___m ___ __-__ ,
- s. .
air. We note that Drell and Belles show the range of deton-ability of H in Air from 18 . 3 V 1 percent to 50 vol percent 2
H.2 We could find no information on the effects of inert -
diluents on the detonability of hydrogen-air mixtures, and we note the caption on the Shapiro-Moffette ternary mixture chart: " Assumed Detonation Limits." We conclude that the effects of steam on detonability of H -air mixtures are 2
essentially unknown. The nearest information we could find was cited by'Keilholtz, and this pertains to detonations in Knallgas-team mixtures (6). Knallgas is a stoichiometric mixture of H 2 and 0 .
2 In reference (6), experiment's indicated that a minimum of about 65 vol percent Knallgas in saturated steam at 100'C was required for detonation. This would correspond to about 44 percent H
- 2 The occurrence of detonation is also influenced by the size and config'uration of the vessel, and the nature of the walls (4,7), which further complicates efforts to predict detonation precisely.
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REFERENCES
- 1. G. W. Keilholtz, " Annotated Bibliography of Hydrogen -
Considerations in Light-Water Power Reactors, ORNL-NSIC-120, Feb. 1976.
- 2. Z. M. Shapiro and T.- R. Moffette, " Hydrogen Flammability Data and Application to PWR Loss-of-roolant Accident,"
WAPD-SC-545, 1957.
- 3. Sir Alfred C. Egerton, " Limits of Inflammability," Fourth Symposium (International) on Combustion, the Williams and Wilkins Co., Baltimore, 1953, pp. 4-13.
- 4. I. L. Drell and F. E. Belles, " Survey of Hydrogen Combus-tion Properties," National Advisory Committee on Aero-nautics Report 1383, 1958.
- 5. H. F. Coward and G. W. Jones, " Limits of Flammability 'of Gases and Vapors," O. S. Bureau of Mines, Bulletin 503, 1952.
- 6. J. A. Luker and E. C. Hobaica, "Effect of the Initial Mixture Density on the Formation of Detonation in Knallgas
~
Saturated with Water Vapor," Journal of Chemical and Engineering Data, 6, 2 April 1961, pp. 253-256.
i
- 7. L. B. Adler, E. C. Hobaica, and J. A. Luker, "The Ef'fect of External Factors on the Formation of Detonation in Saturated Knallgas-Steam Mixtures," Combustion and Flame, 3, 481, 1959.
- 8. A. - L. Furno, E. 3. Cook, J. 11. Kuchta, and D. S. Burgess, "Some Observations on Near-Limit Flames," Thirteenth Symposium (International) on Combustion, 1971.
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APPENDIX B HYDROGEN-AIR MIXING BY FAN ,
i Air recirculation fans are provided in the Sequoyah con-tainment for returning air to the lower compartment after a postulated blowdown. Two such fans are provided, each having a rated capacity of about 40,000'cim. The purpose of the fan-induced cecirculation is to convey steam produced by residual heating to the ice condenser, if the emergency core cooling system should fail (failure of the ECCS is also a situation that could permit a zirconium-water reaction and hydrogen generation). The design basis for the recirculation system is an air flow rate of 40,000 cfm, corresponding to the cperatica. of one fan. Some parataeters related to mixing and burning of hydrogen in an air flow of 40,000 cfm have been calculated, and are presented in Table 4. t The air velocities in the ice condenser and upper plenum are low. Nevertheless, the flow would be turbulent in the upper plenum of the ice compartment, so the flow entering the 1 upper compartment should be well mixed. If hydrogen were being generated by a 1% per minute reaction of zirconium (as an example), the rate of hydrogen flow would be about 10% of the air flow, giving a mixture containing about 9% H2. This would be combustible, according to the literature cited else-where in this report.
A reference calculation is illustrated in Figure 2, where mixtures of 40,000 cfm air and the hydrogen yields of various rates of zirconium reaction are plotted on the ternary mixture chart. Each reaction rate corresponds to a straight-line ' locus, with steam rate determining the position on any line. The one point plotted on 'each line is for a steam rate that corresponds to the heat release rate o.f the Zr-H 2O reaction and the latent
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. heat of vaporization of water. It can be seen in Figure 2 that the yield of 2r-H 2 O reaction rates in excess of 26 per .
minute can produce detonable mixtures with 40,000 cfm of air if the steam content is sufficiently low. Rates of several percent per minute were calculated for some accident scen-arios in WASH 1400.
e 0
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B-2 S
Table 4. Air Circulation Parameters Design Data From Sequoyah PSAR .,
Number of Blowers 2 Capacity of Each Blower 40,000 cfm Ice Condenser: Flow Area (net) 1,326 ft 2 Height 49 ft Annular Thickness 11 ft Effective Circumferential Length 267 ft Lower Compartment Active Volume 2.87x10 5 ft 3 Total Containment Active Volume 1.24x10 6 ft 3 Derived Parameters, for One Blower Operating Air Velocity: a) In Ice Bed 30 ft/ min b) In Upper Plenum of Ice Compartment 14 ft/ min Air Reynolds Number in Upper Plenum 2.6x10 4
air (kinematicviscosityog/
9 50*C = 1.15x10-2 ft min)
, Air Residence Time in: Ice Compartment 1.6 min
- Lower Compartment 7.2 min
. : Total Active Volume 31 min of Containment i l l
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l 1
- - . _ - . - . . -. - - - ~ ~ _ _ . . - - - - -
s
m .. .
100% air .
\\ - Zirconium reaction
\' rates, percent / min
\
X / .5 0 N ,N x 1.0 Assumed -
detonation
\ \
limit N \ ,
h, 2.0 N
Flammability N
N 0.0 20% air N 4\
e & \\s 3 p s
, 100% H2 100%
steam Limits of flammability and detonation based on Shapiro and Moffette WAPD-SC-545, as reproduced .in WASH 1400.
Figure 2. Locus of state points for mixtures of 40,000 cfm air with the hydrogen yield of various zr reaction rates. ;
l B-4 l .
,