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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
[Table view] |
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400 Chestnut Street Tower II July 17, 1980 Director of Nuclear Reactor Regulation Attention: Mr. D. G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Eisenhut:
In the Matter of the ) Docket No. 50-327 Tennessee Valley Authority )
Enclosed for your review are 41 copies of the documentation requested by your staff during the TVA-NRC meeting on July 2, 1980, concerning the fire protection modification schedules for the Sequoyah Nuclear Plant unit 1.
As stated in Enclosure 1, there are seven modifications with completion dates after November 1, 1980. TVA considers these modifications as enhancements to the defense in depth concept, none of which are required to ensure safe shutdown of unit 1 in the event of fire. Three of the modifications are related to protection of a system, the Essential Raw Cooling Water System, which is not required for unit 1 operation. Three of the modifications are improvements on existing fire protection design )
features which are made to enhance safety. One of these modifications, cable coating of additional cables, will be done according to the NRC staff criteria for addition of cables during the operation of any nuclear plant.
If the NRC staf f does not concur in the TVA position t'.at each of these seven fire modification schddules are acceptable without a formal excep-tion to GDC 3 of Appendix A to 10 CFR Part 50, TVA hereby asks for an ;
approval of schedule of these modifications as stated in Enclosure 2. l Very truly yours, l
TENNESSEE VALLEY AUTHORITY j
}%/},
L. M. Mills,. ager k# .
Nuclear Regulation and Safety k )
Enclosures 1 1
Tms DOCUMENT CONTAINS POOR QUgtgg PAGES 8007230997 "
F - -
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EMCLOSURl; I
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S13!UOYAll NUCLEAR 'PIANT JUSTIFICATION FOR COMMITMENT COMPLETION DATE BEYOND NOVEMBER 1, 1980
- Act. i nri 'or M<xli fication Requirmt Junt.l fica t ion
- 1. (a) Enclose exposed _ conduit Interim protective measure identified ira Table 1.4 provided through the availability of the auxiliary with a 1-1/2-hour fire essential raw cooling water barrier.
(AERCW) system as backup to ERCW system.
(b) Reroute train B ERCW pump power cables and ERCW xfmr power cables from top of -
ERCW J-box to obtain minimum 20 feet separation from train A.
(c) Enclose ERCW junction box with 1-1/2-hour fire barrier.
3.B (ii) Install additional fire dampers Five dampers involved, four in required as a result of NRC concerns the control building at elevation of February 12, 1979, meeting. 685 and one in the auxiliary building associated with the refueling purification filter room. Those in the control building do not pose a threat to safe plant ehutdown due to the provision of the backup control room and the establishment of emergency operating instruction (E0I-7).
The single damper from the refueling purification filter rooms poses no threat to safe plant shutdown. The filters
- are required only after shutdown, ,
during refueling operations or fuel transfer. .
3.B (iii) Coat'the metal barrier plate in TVA tests have demonstrated than l cable tray penetrations with the as-installed cable tray l pyrocrete. penetration seals provide a fire l resistive rating consistent with !
the designed rating of the l penetrated barrier itself. l t
1 e
-j
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f Table 1 JUSTIFICATION -FOR COMMITMENT COMPLETION DATE BEYOND NOVEMBER 1, 1980 Action or Modification Required Justification
- 4. ' Coat exposed surfaces of cables Approximately 95 percent of all with flame retardant material cabling requiring coating in in areas outside primary unit 1 and comt:0 areas has been containment containing one or both coated and is continuing as safety-related divisions. additional cable is installed.
The completion date of 12/20/81 reflects cable coating requirements resulting from modifications for unit 1, i.e., .
nit 2 reactor building annulus.
9.D Provide additional sprinkler heads Installation of additiona.1 or relocate existing heads to clear sprinkler heads has been overhead obstructions. completed in the more sinnificant areas of concern by the staff reviewers, i.e., area beneath mezzanine around the component cooling water pumps, the ERCh' junction box, and the motor-driven auxiliary feedwater pumps.
The relocation of existing heads to clear overhead obstructions and provisions of additional sprinkler heads for the remaining plant areas will require a case-by-case field inspection and resolution.
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FURTHER JUSTIFICATION AND COMMENTS TVA believes the presently implemented Sequoyah Nuclear Plant Fire Protection Program to be in compliance with General Design Criterion 3 of Appendix A to 10CFR, Part 50, without the implementation of those commitment items listed in table 1 before November 1, 1980. TVA considers these items as enhancements to the defense in depth concept, none of which are required to assure safe plant shutdown in the event of fire.
Items 1(a), 1(b), and 1(c) are intended to assure availability of the ERCW pumps for a period sufficient to allow the fire brigade to control and extinguish a fire in the area of the affected circuits assuming the installed automatic suppression systems fail to operate as designed. TVA has provided the auxiliary essential raw cooling -
water system (AERCW) as a backup to the normal ERCW system and developed procedures (SOI 67 2) for its alignment and use in the event the normal ERCW system is unavilable due to fire damage. A description of the AERCW system is provided in the Sequoyah FSAR, Section 9.2.2.
This approach is consistent with item 2 3 of the staff requirements, i.e. , "where modifications will not be implemented for an extended period, interim protection measures should be required to compensate for the lack of protection."
Item 3.B(ii) is intended to minimize fire damage to the main control room complex and one area of the auxiliary building by the provision of four additional fire-rated dampers in the unit 1 and unit 2 auxiliary instrument rooms and one additional damper in the auxiliary building refueling purification filter rooms. The provision of thesc
' dampers is not essential for safe plant shutdown in the control builcing auxiliary instrument rooms because, as indicated in the response to ASB question 18, the auxiliary control roem complex and
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' corresponding Emergency Operating Instruction E0I-7 provides for safe plant shutdown should the main control room, cable spreading room, ror the auxiliary instrument rooms become damaged as a result of fire.
The refueling purification filters are required only after shutdown, during refueling operations or fuel transfer.
Item 3.B(iii) - TVA's response to ASB question 3.B(111) provides a
, detailed description of the Sequoyah electrical penetration fire stops for cables and cable trays and the tests conducted to qualify the penetrations. The staff's Safety Evaluation Report - Supplement No. 1 dated February 1980 (NUREG-0011, Supplement 1), Section 9.5 III B, states that the construction features of the electrical penetrations have been reviewed and that the staff had concluded that the applicant has provided tout documentation to demonstrate the fire resistivity of the electrical penetrations. However, the* staff requested that the bare steel plate in the cable tray penetration seals be coated with a fire resistent coating equivalent to the fire barrier rating, _.Lo provide increased annurance of protection. TVA agreed that,in loin of further discussion of test docunentation and in the-interest ,
of defense in depth, TVA vould agree to provide such a coating as soon as possible.
3 k .
TVA ius concluded that no threat to safe shutdown capabilltr. exists as a renuit of the installation of fire-renistive coatinns not beenin; applicd 1-v ;iovembor 1, l'8M.
Item 4 - Approximately 95 percent of all installed exposed cablins requiring coating in unit 1 and common areas has been coated. The 5 percent'which is installed and not yet coated represents those.
cables numbering less than 10 in a single tray run. The 7aC staf f previously agreed that up to 10 additional cables within any single tray run can be added before additional coating is required. The December 10, 1981, completion date for this item reflects cable coating renuirenenta resulting from nodificatione, associated with unit 1, i.e.. anythine from T!!I, and relating to unit 2 specific areas. based on the above discussio:1, this cotmitment is complete for those areas pertainin;; to unit 1 operation.
Item 9D - The installation of additional sprinkler coverage for the area under the mezzanine for all component cooling water pumps, under the pipe break barrier for the auxiliary feedwater pump, and the area around the ERCW box has been completed. These were the areas of greatest concern to the NRC staff during the site review.
The relocation of existing heads to clear overhead obstructions and provision foradditional sprinkler heads for the remaining plant areas will require a case-by-case field inspection and resolution. The philosophy for the design of the sprinkler systems at' Sequoyah including the location of individual sprinkler heads was to afford maximum protection for exposed cabling. During NRC-sponsored tests conducted at Sandia Laboratories it was determined that internally generated cable fires do not propagate to adjacent trays provided that Regulatory Guide 1 75 separation is maintained and cable meeting the fire-retardant requirements of IEEE 383 is used or non-IEEE 383 cable with an approved fire-resistive cable coating is used. The results of the Sandia tests have deemphasized the importance of .
providing maximum water coverage to exposed cable surfaces and shifted the emphasis. to providing maximum water coverage to the floor area beneath cable runs in an attempt to deal with the exposure fire potential, both installed and transient.
TVA agrees with this more recent philosophy and has committed to relocate existing heads and/or provide additional heads to provide clear coverage to the floor area to the degree practical.
However,.TVA feels that:the as-installed sprinkler systems provide adequate protection to the circuits and equipment they were designed to _ protect and, in the event of an exposure fire resulting from installec (n transient combustibles, that these circuits and equipment will be protected for a sufficient period to allow the fire brigade l to extinguish the exposure fire using the manual equipment provided.
Therefore, no threat to safe shutdown capability exists in the interim period betore compiction of this cotuaitment.
.E30191.03 4
t tu:1.uSill:1; /
SEQL'OYAH NUCLEAR PLANT FIRE PROTECT 20N SCHEDULE HISTORY TVA first submitted a proposed schedule for the completion of all modifications resulting from c:3==itments made in our submittal of
- January 24,' 1977, those result.ng from nonconfor=ance report SWP-78-S-2, and those resultin g from TVA responses to Auxiliary Syste=s Branch Fire Protection Review Questions by letter from J. E.
Gilleland to S. A. Varga dated March 8,1979 (See schedule 1, attached.) This schedule was based on an estimated fuel load date of July 1, 1979, and was reviewed and approved by the staff. -
TVA revised the above schedule on October 19, 1979, to reflect an estimated fuel load date of December 1979 and submitted the new schedule as a part of revision 4 to TVA responses to ASB Fire .
Protection Review Questions by letter from L. Me Mills to L. S.
Rubenstine dated October 23, 1979 (See schedule 2, attached.) This schedule was based on an estimated fuel load date of December 1,1979 t TVA revised the schedule a second time to reflect an actual fuel load date of March 1, 1980, and to reflect additional schedule slippages resulting from the inclusion of some TMI-related modifications. The new schedule also reflects actual completion dates for the mjority of. items .as well as a change in the commitment relating to ASB Question 1. The method of protecting the ERCW power circuits has been changed. This schedule was submitted by letter fren L. M. Mills to L. S. Rubenstein dated June 11, 1980. (See schedule 3, attached.)
TVA believes the new schedule is consistent with the previously approved schedulen considering the slippage in fuel load date and the inclusion of TMI-related modifications and reflects our original intent to complete the remaining fire protection modification ,
commitments as soon after initial fuel load as is practical. -
Justification for completion of the remaining seven uncompleted commitment modificatior.s, three of which relate to the protection of the essential raw cooling water (ERCW) system power circuits, beyond November 1, 1980, is provided in table 1 (attached).
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.t PONSG TO ASli QUESTIONS IIASED ON ESTI!!ATED FUEL LOAD DATE
.. , y 79 SCHEDULE FOR COWIITME!1TS All modifications resulting from commitments made in our submittal of ,
January 24, 1977, shall be impicmented prior to the initial fuel icading
- of the associated unit.
TVA proposes to impicment modifications resulting from faonconformance Report SUP-78-S-2 and from commitments made in this docu ent per the follouing schedule:
ASB D: sign Construction .
(c.Tpletion Completien l
- (f.testion Date Date -
I:0. Action or !bdification Pequirgd 1 Rercute conduit and cable identified
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G/30/79 9/30/79 in Tabic 1.2. See note 1 Urap instrusentation conduit identi- 6/30/79 9/15/79 fied in Table 1.3 with 1-inch-thick Kaowool Blanket.
En[loseexcosedconduitidentifiedin 7/ 31 /75 11/30/79 Tatile 1.4 with a 1-1/2-hour fire barrier.
Develop casualty procedurcs to bring 8/ 31 /7 9 12/31/79 plant to safe cold shutdown with fire damageLto cabling identified in Table 1.5.
Enclose cables identified in Figure 7/31 /7 9 11/30/72 1-2 with a 1-hour fire barrier con-sisting~of 2-inch-thick Kaowool M Board.
Install additional. fire doors iden- - See note 2 3B(i) tified in t:onconformance Report SWP-73-5-2.
Install remaining fire doors iden- - See note 2 tified in Tchic 3B(i)-3. '
~3B(ii) Install additional fire dampers - See note 2 identifed in lionconformace Report SWP-78-S-2. .
Install remaining fire dampcrs iden- 6/30/79 8/31/79 tified in; Table 3B(li)-3.'
' Add pyrocrete to fire dampers PCO -
_ See note 2 17A and 0-31 A-14B.
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9
C I:DUI.l; I (ctm t i smeel)
- ' Construccion
- Design ASB Completion Comple tim Question Date Isa t e
,_,Jin .
Action or Ibdification Requi_re_d, 1
~ 10/31/79
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3B(iii). Coat the rnetal barrier plate in cabic 6/30/79 tray penettations with pyrocrete.
6/30/79 See note 3 4 Coat exposed surfaces of cables with finme retardant material in areas
one or both safety-related divisions.
Install fixcd self-contained If ghting 7/ 31/79 12/31/79 6
in arcas that riust be manned for safe cold shutdown and for access and cgress .
routes to and from all fire arcas.
Electrically supervise the fire protec- 7/31/79 10/31/79 7
tion power distribution panel for loss of pouer. .
Electrict11y supervisc the fire pumps 7/ 31/79 10/31/79 8
for icss of line pouar end motor running condition.
Prov'ide additional sprinkler heads 8/31/79 See note 3 9D -
or reloccie entsting heads to cicar overhead obstr uctions.
Enciese ERCil junction box with 1-1/2- 7/31/79 9/30/79 11B ~
hour fire barricr.
7/ 31 /79 9/30/79 Provide e 1/2 hour fire barrier of 1-inch 1:w.: cal I;1ontet between re-dundtnt power cebles in the ERCil junctionbox.
Provide i.utomatic sprinkler protec- 7/ 31/71 3/31/00 13B u tion under the pipe break barrier -
for the auxilicry feedwater pumps.'
' Provide automatic sprinkler protec- 7/ 31/79 3/31/80 13C.
tion under the rezzanine for all component cooling water pumps.
. Provide a 1/2-hour fire barrier 7/ 31/79 3/31/00 13D
- between train A and D component cooling uater pumps.
Provide.cdditional smoke detectors to 7/ 31/79 3/31/00 13F-actuate tha sprinkler systems.in TVA responses to questions 138 and 13C.
Provide heat detectors in the Eittil 7/ 31/79 10/31/79
- 14 ,
pump rooms of the intake pumping station.
necons
SCllEDl'LE 1 (continued) f 2
w ASD Design Construction Completion Completion Question Date flo. Action or !!ortifir.ation I:cquired _ Date 16 l' ovide Ig.it .1.u m an,I annunt.iation for 7/31/79 11/30/79 loct-out of diesel generator room and board room C02SYSIC*S*
17A P.emove sliding fire doors for 8/31/79 10/31/79 diesel generator rooms and replace with normally closed fire doors.
20A Replace the translucent panels in -
Sec note 3 I!CR with material that meets the -
guidelinesofsectionC.4.a(4)of Revision 1 to BTP 9.5-1.
200 Replace the existing 1/2-inch riser 7/ 31/79 9/30/79 nipples with 1-inch nipples in the records storage area.
26 Provide equip. Tent for fire equipment 7/31/79 10/31/79 houses.
. 21 Relo'cate fire pump separation relays 0/ 31/79 1/31/80 to achieve 20-foot spatial separation.
- Install curbs at doors to transfer 6/30/79 7/31/79 switch rooms of the cuxiliary control compiex. ,,
flnt es:
- 1. Construction completion date is based on arstmptior, that five days will be available at operation node 5 or 6. .
- 2. Prior to initial fuel loading of the associated unit. .
- 3. End of first refueling outage for unit 1.
9 e
e 707193
SCl;EDULE 2
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RLY1SinN 4 Or 'lVA RESPONSES TO ASB QUESTIUNS BASED ON ESTI!!ATED FUEL LOAD DATE
--- -- - UF Di Cifil,UR 1. 19 7 9 SCllEDULE FOR C0'411TMEllTS All modifications resulting from conditments made in our submittal of January 24, 1977, shall be implemented prior to the initial fuel loading of the associated unit.
TVA proposes to implement r.:odifications resulting from rionconformance Report S!IP-78-5-2 and from commitments made in this document per the following schedule:
ASB Design Construction Question Completion Completion
!!o. Action or Modification Required ,
Date Date ,
1 Reroute conduit and cable identified 7/9/79 10/5/79 in Table 1.2. (unit 1) 7/9/79 See note 1 (unit 2)
!! rap instrumentation conduit identi- 5/9/79 10/5/79 fied in Table 1.3 with 1-inch-thick (unit 1)
Kaowool Blanket. 7/9/79 See note 1 (unit 2)
Encicse exposed conduit identified in 12/1/79 4/1/P:
Table 1.4 with a 1-1/2-hour fire barrier.
Reroute units 1 and 2 pressurizer 5/7/79 10/5/79 htr 6900Y power cables to achieve 20 feet spatial separation. .
3B(i). Install.. additional fire doors iden- 3/6/79 See note 1 tified in ionconformance Report
. 51!P-78-S-2.
' Install remaining fire doors iden- 3/6/79'
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See note 1 tified in Table 3B(i)-3. ,
. l Ins';all additional fire dampers 3B('ii) 3/6/79 Sae note 1 ide1tifed in !!onconfont. ace Report SWP 78-5-2. l Install remaining fire dampers'iden- 6/26/79 10/5/79 tifiedinTable3B(ii)-3.
1 Add lpyrocrete to fire dampers PC0 3/7/79 10/5/79 l 17A and 0-31A-148. ',,
. Install additional fire dampers . 12/31/79 See. note 2 required as result of I!RC concerns of february 12,1979, meeting.
SCall:Dif f.1: :' ( comtil e t eil)
ASB Design Construction Completion Completion Question flo. Action or Modification Required Date Date 3B(iii) Coat the metal barrier plate in cable 12/1/79 4/1/
tray penetrations with pyrocrete.
4 Coat exposed surfaces of cables with 12/1/79 See note 2,3 flame retardant material in areas ou; side primary containment containing one or both safety-related divisions.
6 Install fixed self-contained lighting 7/10/79 10/5/79 in arcas that must be omnned for safe cold shutdown and for access and egress - '
routes to 'and from all fire arcas.
7 Electrically supervise the fire protec- 7/9/79 11/7/79 tion power distribution panel for .
loss of power.
8 Electrically supervise the fire pumps 7/9/79 11/7/79
'for loss of line power and motor running condition. - . .
9D Provide additional sprinkler heads 3/31/80 See note 2
. or relocate existing heads to clear overhead obstructions. i 11B Enclose ERCU junction box with 1-1/2- 12/1/79 2/1/80 hour fire barrier.
Pr5videa1/2-hourfirebarrierof 6/29/79 10/5/79 l-inch I'aowool Blanket between re-dundant power cables in the LRCW junction box.
13B Provide automatic sprinkler protec- 7/9/79 10[5/79 e <
tion under the pipe break barrier for the auxiliary feedwater pumps.
13C. Provide automatic sprinkler protec- 7/17/79 10/5/79 tion under the mezzanine for all component cooling water pumps.
13D 1:rovide a 1/2-hour fire bar.icr 7/9/79 10/5/79 between train A and B component cooling water pumps. ,
13F. Provide additional smoke. detectors to 7/9/79 10/5/79 actuate the sprinkler systams in TVA ;
responses to questions 13b .nd 13C.
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SCl!EDULE 2 (continued)
.^
Design Construct on ASB. Completion
- Completion Question Date Date No. Action or Modificatinn Required 16 Provide MCR alarm and annunciation-for 7/9/79 10/5/79 lock-out of diesel generator room and-board. room CO 2 systems.
17A- Remove sliding fire doors.for 12/1/79 2/l/80 diesel generator rooms and replace
'with-normally closed fire doors.
.20D . Replace the existing 1/2-inch riser 6/21/79 9/21/79 nipples with 1-inch nipples in the ,
records storage area.
26' Provide additional equipment for 8/10/79 10/16/79 fire equipment houses.
27 Relocate fire pump separation relays 7/9/79 11/7/79 to achieve 20-foot spatial separation.
- Install curbs at doors to transfer 6/20/79 10/5/79 switch rooms of the auxiliary control compicx.
Notes: ,
- 1. Prior'to initial fuel loading of the associated unit.
- 2. End of first refueling outage for unit 1.
- 3. Cable' coating is progressing. Areas identified in submittal of January 4,1977, will be completed prior to initial fuel loading. .
of the associated unit.
ee
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-2n,in2 I
Mi , - _ ,, . -.
~*--
- AS Suli!!LTTED IN TVA LETTER FROM L. }1r MILLS TO L. S. RUBENSTEIN DATED -
' JUNE 11, 1980 - SCHEDULE BASED ON ACTUAL TUEL LOAD DATE OF MARCH 1,1980
- SCHECdLE FOR C0mlTMEllTS
-All modifications resulting from coamitments made in our submittal of January 24, 1977, shall be icp'.amented prior to the initial fuel loading of the associated unit. ,
TVA proposes to implement modifications resull[ng from !!onconformance Report SWP-78-5-2 and from commitments made in this document per the following schedule:
Design Construction ASB Completion . Completion Question Date Date No. Action or Modification Required .
l' Reroute conduit and cable identified 7/9/79* 10/5/79* -
in Table 1.2. (unit 1) 7/9/79* See note 1 (unit 2)
Wrap instrumentation conduit identi- 7/9/79* 10/5/79*
ficd in Table 1.3 with 1-inch-thick (unit 1)
Kaowool Blanket. 7/9/79* See note 1 (unit 2)
Encle:e exposed conduit idantified in. 9/1/80 6/30/81 Table 1.4 with a 1-1/2-hour fire barrier. __
+
Reroute units 1 and 2 pressuri:cr 7/7/79* 10/5/79*
htr 6900V po,er cables to achieve 20 feet spatial separation.
Reroute train B ERCH pump power cables 8/1/80 4/30/81 and ERCH xfmr power cables from top of -
ERCW J-box to obtain minimum 20 ft.
separation frem train A.
3B(i) Insta 1 additional fire doors iden- 3/6/79* 11/15/79*
tified in f!onconformance Rcport SWP-78-S-2.
Install remaining fire doors iden- 3/6/79* 11/15/79*
-tified in Table 3B(i)-3. ,
3B(ii) Install additional fire 6 mpers 3/6/79* 11/15/79*
identified in lionconformance Report-SUP-78-5-2.
, Install remaining' fire dampers iden- 6/26/79* 10/5/79*
tified in Table 33(11)-3.
Add pyrocrcte to fire. dampers PCO 3/7/79* 10/5/79*
17A and 0-31 A-148. .
Install additional fire dampers 10/1/80 11/1/81 required as result of NRC concerns of
. -February 12, 1979, meetin9
ASB Design Construction Completion Ccmpletion
. Question Date Date tio. Action or Modification Recuired Coat the metal barrier plate in cable 8/1/80. 10/31/81 3B(iii) tray penetrations with pyrocrcte.
4 Coat exposed surfaces of cabics with 7/1/00 12/30/81 flame retardant material in areas #
outside primary containment containing one or both safety-related divisions.
6 Install fixed scif-contained lighting 7/10/79" 10/5/7.o
- in areas that must be manned for safe cold shutdown and for access and egress routes to and from all fire areas.
7 Electrically supervise the fire protec- 7/9/79* , 11/7/79*
tien p0wer dlstribution panel for loss of power. ,
8 Electrically supervise the fire pumps 7/9/79* 11/7/7S* ,
for loss of line power and motor running condition. ,
90 Provide additional sprinkler heads 10/1/80 11/1/S1 or relocate existing heads to clear overhead obstructions.
11S Enclose ERCW junction box with 1-1/2- 9/1/80 6/30/53 hour fire barricr. ^
Provide a 1/2-hour fire barrier of 6/29/79* 10/5/PIF*
l-inch Keowool Blanket between re-dundant power cables in the ERCW .ws junction box. ,
133 Provide automatic sprinkler protec- 7/17/79* 10/5/73*
- tion under the pipe break barrier for the auxiliary feedwater pumps.
13C Provide automatic sprinkler protec- 7/17/79* 10/5/79*
tion under the mezzanine for all component cooling water pumps.
13D Provide a 1/2-hour fire barrier 7/17/79* 10/5/79*
between train A and B com;;acnt cooling water pumps.
~13F Provide additional smoke detectors to 7/17/79* 10/5/79*
actuate the sprinkler systems in TVA -
responses to questions 13B and 13C.
4 l
855301 .
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SClllCDt!LI, 3 (continueil)
Design- Construction A50 Completion Completion Question Date Date No. ~ Action or Modification Recuired ,
Provide MCR alana and annunciation for ?/9/79* 10/5/79*
16 lock-out of diesel generator room and ' '
board room C02 systems.
Remove sliding. fire doors-for 2/12/80* 8/1/80 17A diesel generator rooms and replace
- with normally closed fire doors.
Replace the existing 1/2-inch riser 6/21/79* 9/21/79*
203 nipples with 1-inch nipples in the records storage area.
Provide additional equipment for 6/5/80 6/10/80 .
26' fire equipment houses. ,
27 I:clocate fire pump separation relays 7/9/79*
~
11/7/79* .
to achieve 70-foot spatial separation.
- Insta11 curbs at doors to transfer 6/20/79* 10/S/79*
switch rooms of the auxiliary control complex.
Notes _:
- 1. Prior to initial fuct loading of the associa'ted unit.
- Indicates actual finish date. .
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