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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] |
Text
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TENNESSEE VALLEY AUTHORITY -
CHATTANOOGA. TENNESSEE 37401.
SN 1578 Lookout Place December 8, 1986 Director of Nuc' lear Reactor Regulation Attn: Mr. B. J.'Youngblood, Project Director PHR Project Directorate No. 4
' Division of Pressurized Water Reactors (PHR Licensing-A)
U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Youngblood:
In the Matter of the )' Docket Nos. 50-327 Tennessee Valley Authority ) 50-328
, SEQUOYAH NUCLEAR PLANT (SQN) - CABLE PULLING QUESTIONS: SUPPLEMENTAL RESPONSES An interim response to your letter dated August 29, 1986 to S. A. White was f provided by a letter from me to you dated October 31, 1986. This-letter /
provides the balance of the information requested in your August 29, 1986 j letter.as well as some additional information on the resolution of the concern regarding support of cables in vertical conduits. Enclosure 1 contains TVA's
. final response to questions 2 through 5 which were outstanding in TVA's interim response.
At.the July 17, 1986 meeting in Knoxville between your reviewers and TVA, TVA agreed to provide its cable sidewall bearing pressure tests (SWPT) report upon completion of a third-party review. This third-party review is now complete.
Enclosure 2 contains TVA's SWPT report.
The SHPT report details an extensive testing program undertaken by TVA to determine the maximum allowable sidewall bearing pressure values for various different cables. These cables are representative of cable procured from the many manufacturers and installed in the various voltage levels in all of TVA's nuclear power plants. These tests conclusively established allowable SWPs in excess of_that previcusly specified by the cable industry and/or manufacturers. The test results were consistent with recent tests performed by Electric Power Research Institute (EPRI) to establish higher SWP values.
The final report from the third-party reviewer, David A. Silver and Associates, states that the higher tested SWPs "had minimal to relatively small effect on the dielectric strength of the cables tested," dielectric strength being " considered as a primary criteria for evaluation of cables subjected to a sidewall bearing pressure test." The report concludes that, "The results of this test program in conjunction with the results of the EPRI ,
sponsored R&D Project 1519-1 can serve as the basis for consideration of higher permissible sidewall bearing pressures for the same and similar cables than the present limits of 300 pounds / foot for power and control cables and 100 pounds / foot for signal and instrumentation cables." '
\
ReA' 188M 8ea88827 F \ \
P PDR y' An Equal opportunity Employer
.g . - -
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, t ' . ,
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2 iDecember8,$986: '
? ~ ! Director.of NucleargReactor! Reg'ulation
- The; minor corrections.noted in the third-party review did not detract from the
.overall conclusionsiof:the report. Tne final' report of1the' third-party:
treview? as well as a synopostsof.the reviewer's qualifications and ~
1
_ lM experience, are enclosure 3. 'The SWP values listed in column 2, page 8, of -
. enclosure 3 represent the correct tested values.
. .TVA has, through the'above testing and analysis, conclusively demonstrated-
[ that the practices employed during the installation of. electrical cable at SQN.
= maintained the adequacy and integrity of the Class 1E cable with~ respect to SWP. In. addition, SHP parameters'in excess of.that previously specified by the~ cable industry and/or manufacturers have been. established. Accordingly,
.TVA intends to revise its installation proceduresLto. allow.for a conservative yet higher fraction of the tested values in its future cable installation.
iThe increased allowable sidewall pressure values are 1000 pounds / foot for-
. power and control' cables, 500 pounds / foot.for-instrumentation cables, and'300
. pounds / foot for coaxial, twinaxial, and triaxial cables. All of these are well within the bounds of'the recent-testing. The effort outlined above ,
concludes TVA's evaluation of cable SWP at.SQN.
- .In enclosure 3 of my letter to you dated October 31, 1986, TVA provided a.
response to concerns on the adequacy of cables-installed in vertical conduit runs. TVA's position was substantiated by the results of a 3-year-detailed experimental and analytical study on cable failure prepared by Sandia Laboratories for the U.S. Nuclear Regulatory Commission. This1 study is entitled,' " Correlation of Electrical Reactor Cable Failure With Materials Degradation," and was printed in March 1986.
As stated in the 0ctober 31, 1986 response, SQN is currently inspecting' all vertical conduit runs which contain 10 CFR 50.49 cables for conformance to the applicable ~ criteria. However, as a result of the test conclusions and the p -correlation to the SQN design presented in the enclosure to the referenced
' October 31, 1986 letter, it is apparent to TVA that this concern no longer represents a significant safety issue.
~
{'
-Accordingly, TVA will continue to pursue resolution of this concern as i previously stated, with completion of the evaluation and implementation of any ;
corrective action, if required, scheduled for the next refueling outage. This concern will be removed as a restart item for SQN.
+
i !
, .. u _A. . . . ~ . - _ , ......-...,-,_--._-.,_-...m._.,_, . _ . . . - _ . . - - , . . _ , . - , . -
m
-December 8,'1986-Director of' Nuclear Reactor Regulation
.Your staff has been k'ept informed of the status of this response. If you have any questions regarding this matter, please get in touch-with M. K. Brandon at (615) 751-8076.
Very truly yours,
-TENNESSEE VALLEY AUTHORITY R. L. Gridle , Director Nuclear Safety and Licensing Enclosures-cc:(Enclosures):
U.S.-Nuclear Regulatory Commission Region II Attn: Dr. J.. Nelson Grace, Regional Administrator
. 101-Marietta Street, Nll, Suite 2900 Atlanta, Georgia 30323
-Mr. Gary'Zech, Director.
TVA Projects'
'U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Carl Stahle Sequoyah Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland '20814 i
y-: . , .- .-
+
4 e
ENCLOSURE 1 i k
W
ITEM 2 Have the worst-case conduits for tough cable pulls been determined for SQN?
If so, supply isometric drawings, pull cards, and work orders for the worst-case pulls (i.e., those which exceed tension or sidewall bearing pressure limits) and for the next worst-case conduits. Conduits in harsh and mild areas should be included in the determination of worst case.
INITIAL RESPONSE A preliminary set of 16 worst-case conduits had been selected. The selection of these 16 worst-case conduits was made by a designer who had 4 been involved with the design of most of the conduits in the Auxiliary Building. His selection was made from conduit and grounding drawings using his judgment as to which conduits he suspected to be worst-case based on the number of bends, long runs, changes in elevation, etc.
Isometrics and sidewall bearing pressure calculations for these 16 have been informally provided to your reviewers for purposes of discussion only.
Because of some concerns about the assumptions used in the preliminary selection, evaluation, and calculations regarding the worst-case conduits, TVA has opted to broaden the scope of its worst-case determination at SQN.
The evaluation at SQN will be in accordance with the guidance provided by TVA's Chief Electrical Engineer in his June 23, 1986 memorandum (attached).
TVA's revised evaluation will consider these original 16 conduits as well as additional potential worst-case conduits. The final worst-case conduits will be selected from this larger group. -
SUPPLEMENTAL RESPONSE The worst-case conduits for tough cable pulls have been determined and ar?
documented in the calculation package, " Identifying Sidewall Pressure Violations" (attached).
Following a detailed reevaluation, five of the original 16 conduits were replaced with ones which better represent the worst-case condition.
Conduits containing 10 CFR 50.49 cables in all structures, in both mild and harsh areas were included in the selection process. Isometric drawings and, for conduits with multiple cables, copies of pull cards and II28 carJs are included in the calculation package.
- . h
TvA 10697 (DNECJI61 . DNE CALCULATIONS c5[s[o'n"0 hh**,"
g*
m L. -
p*mNTiuNiT Iden+ifvino Sidewall Pressure Violations .g- .Saouovah 142 PREPARING ORGANIZATION 6 KEY NOUNS (Consult RIMS DESCRIPTORS LIST) I SGEP E-2, EEB Sidawall 3ressure Vielaffons .
BR ANCH/ PROJECT IDENTIFIERS Eac these calculat. ons are assued. pro 6are, asure that the original (RO) RIMS eccession -
S GW - t3. 2-01,5~
a
" ' RiuS'usei g RiuS acension nun,bu APPLICA8LE DESIGN DOCUMENT (S) 860731C001 kB25 86 0724 's o 1 R4 6 4C0013(9ga 3 861112 8oo a3 SAR SECTION(S) UNID SYSTEMts)
IB 2 .5 861203 8 fU R-Revision 0 R1 R2 R3 Safety < elated?
ECN No o scate Not Applicable) YesO No O p,,,,,,o D.T. Kirk 7.zw pgg gg n.,o.g u naq.s Choose _ and analyze condull.s
.wilh malfipie bends behacen Q%&7-24*jfRy pulI >oints to deiermine.
tuheNer maximon sidewall S$
Rev " ' ' ' ' ' " af a- $.,eph. W t pressures for electrical
' oat.
""' % t j ,x &6 %gadil~ cable have been exceeded 6N 7-2-v s? /
INI-r/o n +f as required ggnggfc gcq by;g W,3q7 any List all pages added I"7 through g/
g.j by this revision. 727 ge,, ty (o270. j List all pages deleted Q 4ttachineAts
};r,;j by this revision. l 2a M 2P Si! List all pages changed by this revision. l 1 and 2 l j2,+596 1
\ WW5W 22 i
Abstract 5 \
These calculations contain an unverified assumpt ont )_ 727 1
,, that must be verified later. Yes O No B This ccdculc& ion +cok the da+o, found durinc a field walkdown of conduMs and used i+ +o de+erdine if cable cidewall pressures inside tae conduit.s have exceedec.
. the al owable ;5(xteen o9 he. worst cose limi+s as for . before as bendsthe walkdown.ts -
w cho.sen to be stud (iecl. The resul+s) conduiw
- whether or nof WBN
. +o 634,an verifyd 6270 cqely a+ SNPpenertc NCRA- .
foF the ceiginal sixteen cases,Sive were eliminated and cerlaced by new cases +kt g' conduit seleh'en l ql Isbetteru represented the worst case coiidition.The meth I B &plained on the.dached sheef and cable evaluation was bas the memorandum & Tune 23,n86 Lmt WS.Raughley 1ot%se lis+ed.The QA
\ cable oullina recnis & all Ae.com nesoad old were re+cieved +o veriFv
O 2croviim an'd store cSicuiations in Rius Service Ceater.
uncroisim and desirov. O .
E Microfilm and return calculations to: M. d, 8LAN '
Address: D/[p QL/=E.8 ee: RIMS.5L 26 C.K _
4 f,
AfEP-3.I h.2 +
z -8 ldentifyinq3idewaH %sure ViolakonslR.2
~
s.n. P.
LIctrfIca+ ions Ci
- u #]X., it-29-iw -
_ . . _ _ . . - . _ _ _ ~ h +2 4 y Ori inally +ke selections ,walkdown!and calculations we SMk-O-Sl7-32 r.0 g. Musk l(o oS 727.This procedu
- imited the samale to the Auxiliary bull ding. Aher the. .
presentation oE 1he calculation to the NRC. hther investic l was recruiced.To direct us on resubmi+tal wei memorc:ndum Fwen W G. Ra thley 9717 drough 26 of 727. .
1: The emples were wt limited o +neluxiliary Building +hi.s
+ime bu+ Included all 50.% condush in mild and hansh areas. !
Also +he cable pulls were calculafed in two pulline dit'ections anc the pull carel.s and GA reconds of Me cable pulls were u+ilized to verify pullb i
that on +he Q A recock oS -the. c6ble Is, the I.1-2epul'y.s.
aards +ha+ no rope sizes or dynamome+er numbers were i
recorded in +hele designaled spaces +o dencie cable tens 1on
( limiting Tension limiHng devices were called for only on mechanically -assi.s+e8 ylls until 5-3-79 when the xceedure cal ec For all pulling tensions anc. me+ hods i
M be in accordance with G-SEr. Allof the QA record
~~~~ cards in this calcula+1on were sicred >y a certiRed ,
l QA inspec+or and Jafed stating hat"+ht.s cable was L pulled in accordance with revision & aodialde) of +his l Instruction " II-28 In&lly the sam (ples we)re to include. a mini L ;
ger voltage level per uni +.In our evaluafton process of i
l 8etermininc +he worst case. ,we. %nd a v2 conduit- + hat
' a>peared tb be worse fhan +he. V3 sample.s. It was decided to use .6 v2 samples and 3 V3 mmples rather than ,
i -
H each due to +he mor
! values for V2 cables. e limi+ing. allowable pulI tension
~
For embedded condui+ runs case number 10 enly calculates a max 1 mum allowa,ble eullin9. +ensien +naf l may be used at- +haf node. poin+ To achieve. a .5W.P value -for this study embeddec runs were calculafec os exposed (ie two 90* bends and a straic h+ run) .
t
$h
NEP-3.i AW.2 s s
- centifyinc lSicewaDfressure"/rolasonsTR.2C
~ ~
6.Nd .._
(- Cari0ica+ ions Con +'c'. hny ca
.JK n>n
, Domputer Program c.larifications i
' he each node. entered in a.sechn of conduit the case, .-
le radius and r degrees of the nede is used to ca$lebte Tex,p a +1en usin all +he aforementioned s +o cc \cu ate .swP. IS for a a calar nde the answer-
- necative clnted I for tae calculation
.but not used in +he calcu cf Tex $afion next nule as is bf the,it negative. but is set to zero. As stafeJ beere. de.
calculated Texp for each node is used to calculate
+he swP. The last calculated real mlue d SWP Goi necessocil it has not i
exceeded the. highest mIculated e maniacturers recommen value)d SWP in i
any of the revious calculations,is pf as" b r
! Cq u\ated idewall Pressure = t the inni of C
qiven a "CaIcula'af+er xoSram the in>ut cable of th a yo 're l +ed Madm Pulline Force For Tour 6a eenn C6)es . This is"ain arrivedAllowab 4+ by the
- ~' data on the cables inpuHed into the computer and 4ctally I
awt from conduit informa+1on. When it s+ arts calcdakng
- e moxImum allowable alling tens 1on be+ ween pull poinis.
, it is accom lished by e computer in + hts manner....
i The. com u r progg1.gerements the. las+ value of '
i Tex G had a r ca.w w l eS wP) by one untii i+ posi+ive Meer calculated value
~ -For Fmax or SwP anc: then xin+s-%e lasf value i- beGre exceeding Fmax or swP as +he mcurmum .
pu})inc tension b'e.fween these. pull points .
l L
4 J
NEP-31 At2 Identihinc[Sideva ?mssure Vioation R.2 i YS.P.. _
Yehcdo offor $onclu?t Gelec jonT ~~ ~1,)fx% p.n.:ss-L
..- ma
. u 2,-sc AlI co oles (approx. 5600) connec+1no to +he IOCFR509cy j
equipment were identified. A comptder sor+ of all condwk .
(ayptox. 5400) with these. cables roatecl % rough + hem was obtained. A review of +hese condai+s was condxled j from design dn2wincs +o eliminate those that W short len#hs,Je no chan I
more ce the worst c{ase criteria es+ahlished he selec.+ ton bye procecure. When conJm'ts rnee+ine+all did not exist the condw'ts fha + m2 the maj'on,fy of +he criteria were selecFed.This was accompitshed as a firs +
step in the elimination process of findina our worst case conduits and approximately 4775 condWfs were. renved by +his process'.This left ol5 proximately 625 conduifs that were physically walked ciown i walkdown approximately could hal/a the plan be eliminated as not+. Fr meetin s)cetc.g.all on the majority of the criteria without doing hing.
were skA+c% hed forffmginjn{
furt1 er evaluation. From the ske4 7"~ l opproximately 160 were evaluated and -Poun he.
l
- maqority of the.
Sili,tohl degrees eGworse case criteriq bencs between aall pomby length'ts an j , elevation changes.The. coer 150 + hat were sketched were. elimina+ef as nc+ meetino the uers+ case. criferld.
of i
mad +be selec+ ion onocedu/'e.The +yimI selecti e 4 rom he H50 + hat were evduated as nee +tnc the
' C' worst case eriteria. . .
R.2 Ihe oriCina[ Ifo that were Selectec. d6 worsY COSC Werd' C
reevaluated with +he 150. We ended u> mplacinc 5.
V So and 5 now new there are !I d +he cases ceded.The rittenoric%.inal enlanations cades l -for +hese conduits mincl selected as Worst case
- -follows thts 9 age.
i
'*8$
c_5 +6 _
.Icentify+ing Sidewa' Pressure. Vichtions R.2 Sequo Explana )on For Conduits Beinq Selected As_ _ Plant .
[ Wars + Case per section 2.2.I99 22 d.727 w.~~Km lh2%8G
~-- W ,~ itM.W I.
~
.I
' M32.4lB" This A++achmen+
was the con 3,db+ es 27 +hmugh 98. of 72 c.hosen -frem volfoge
- level Il. it has vnultipel bends be+ ween ullpoin+s, .
os rnach as 3OO*.It has a high gerce e of
- cable fill , 28.47 '/o with six cables p . It L cha elevation. It was one of the original sixt en that were. kept.
ilPM4704A- A11achment 4,duit chosen hm This was a con level 2.It has indipie oends be+ ween pull In+s
- as much as 27s"l+ has exceetlect the hi h for, percentage of cable fill,36.01% wie eso1+
cables insYallect.It changes elevaflon.Ifis
( one. of +he oricinal _ sixteen that were kept.
IP 3562 8 - A++achmenf 5, eaaes 176 +hrough 208 of 727
' This was a condui+ ehosen Gorn voltage level 16.It has multiple bends be+ ween pull
. r points as much 46 270?It changes eleva+/on.
> It is th, e. next +o the. worst case we found for I this voltage level. Itis one d +he original srxfeen,
' ' i that were. kept. i IPP575A - A++achrnent 6,e43cs 209 through 219 of 727 ,
- - - - This wds a conduit' chosen fmrn Volfa3e IeVel 14-
~
1 I+ chages elevation. It is the naf to the worst coe. .
I we found fer thu volta Sixteen tha+ wece hej+ge level. It fg one . ;
es 220 +hroa 238 C 727 l
2PL3722A This-is A+tachmenta condai 7'fchosen
- e. level 12.from .It vo has a lonpleu ren+er +han th lengfh~s in G-30,
- Argitfix Fgg. r'th , es elevation.1+ 15
- one of the. c.7.,~ riginal It chagixteen +haf were ke
,--~,,-----,,,,-n-.m-,--e.-- -.-nr--, ,,n,,-.-n.---,-,-----,s -
n,,,-.m,m,,,-, ,.-,,m._ ,,m-
NEP. -3. I a.:2 t.'a ._ ? E Icentifying...Sicewol 3ressure '/lolations R.2 .- Seqa a6 Nuclece Explanahon for Conclulis Beine Selected As ._ . _flant __
( WorsLCase per secRon 2.2.I.n.22 e.727 :- n U-29xe
- e h" tt.2-t&
~
2 es 239 +hna
- 2 3(o37B- A++acament This is a conduit c 8, a@wsen levelfrom /S.L veld i
I has multiple bends be+ ween p ll points,as much .
as 315" lt has a Ion leng , reafer Man +be i length in G-38 App ix F' Ie l. I+ exceeds
- +he. high for per,centoce of cable fil/ 30.2 %.
l It changes eleva+ ion an2 was one. & +he., original I
nirteen that uere.kept.
I
- 2PL3003A-i A++achinen+ 9, mes 2sl ihn,ugh sos a 727 This is a conka+ chosen from voltagelevel 10.
I+ has a lon elevakn.1+g lengA of 104.6 fee + .I+ change were kept.
us one of the crifnal sixteen +his
( es 3o4 +hcoa h 32s 4 727 2PL303, This A- A++achment is a conduit 10, bosen f' rom vold It has mul+)ple bends between pull poinfs,as much as 315'.1+ bas a long lengsk of 110 fee +.1+ has Tr~ !
a hip percen+ age of cabk fil ,29.8%. It changes ;
eleva+ ion . I+ is one or +he orig.inal sixteen the i were kep+.
1 2PPro25A- ThisA++aehmen+
is a conja osenI;lt)es from324 vor+a+hrough e level 14. sse o It has multiple bends be.been pull m+s -
i i
as 360 leng.+h in G-38, Appendix F
- It has a long leng+ kan deTabl .
+he. high for percenta
! It changes elevation .ge of coble. fili sixteen that were kept.
(. G
- i! !
El
-' ~
e
,vcg,,
Pressure Viola' ions R.YL h kuclear 2enHF@"
Explan Sidewain For Conduits Being Se _
xe secfion 2.2J.pg.22_op. 727_ m a-2psc 4 Worst _ Case m.
~. -nWr6 12
- 2V2627A- This f A+tachmen+duiI is a con c e"hes 339 +hcough 400 of een -From voltage level 10.
It has multiplebends befu;een pull pmts as much .
I as 260 It exceeds the high for porcen,tage of i ca ole Sil, , 36.82 % wi+h five cables installecl.I+
l changes eleva+ ion . It is one of the original sixteen that were kep+.
!2PMl8Holli- Anachment 13. nays 401 through 418 of 727 l This is the condmf chosen from volfage level 8.
It exceecls the limit of so between pdl points with one secflon having 412*of bends.
It has a long. length greatec +han the lengfh in 6-39,Ap I+ is one.eenaix F Tab'le3. .e It chance
( ond -founcl to be a worse case.It rep 4ceci I ene ol' +he original sixfeen.
~~
23M185HI This - /ttachment is +he condai14'+eaces 419 +hrough 448 of
%sen frorn voltage level (o.
! It emeeds 1he limi+- of 3(o0* betu>een pulI with one secfion havig yaro" of bends.l+poinls has a long len greder +han +he leng+k in G-38 i
Appendixis onecasesthaf ae new of +c Table 3. I1- change us evaluafed i and -Found to be a worse case..It .replaad one a-P 1he original six+een. .,
2PWl4Sco11- Attachment is, nges 449 +hccugh 487 af 727
- This isihe.conduF chosen froin vol+ age level 7.
It exceeds the. lindt e 360 between pull
,. points wik one secticn having 3(o(o bends total.
L c' I+ has a h le th oF 203 k+. It changes ai elevations."It is one oF the. new cases + hat was
- ekalua+ed foud +o be a worse. case,and replaced '
= one of the. orichal six+cen.
\ >
IE ^%f.g
,, s
- cenW IndESidewah Ex>\anakioh' For Condui4s Being Pressure.%ation Selected As .._ Elo f WorstCaseL persection 2 2. l..pg.22 oL727-teK., &29i8G c...~,
tw. >nn
- 2PlV 472GA- Affachment 1/o,pages'188 thmugh 548 of 727.
This It hasisa along conduct cbsen fram legth greater than vohg+ehe leng.+h level 2 in G-38 Appenchx f Table 3. It exceeds
+he high for percentage of coble fill I
I+ chays e'levafion. I+ is one of the,3ro.8 original l sixteen tha4 were kept.
599 arough 595 of 727.
IMC FimThisBis-theAmchment l
con 17,Nt chosen It has mulkple bends between ull pants,as much as 31o*.1t has a l 1 +h areater than the length in G-38 dix F" Table I.
1+ chances Elevation. It is one of +he new C cases +h'at was evaluated found to be a worse case , and replaced one oY the.6riginal suxteen.
MC15434 -- Afachmen+ 18, page.s 596 through 727 of 727, This is a conduff chosen feorn Wol+ age level 12. '
i It has mul+i le bends bettueen all poin+s as '
i much as. th reader It changes than. the ) 'e;fh leva + ion in G-387*.
epen is one .
ble 1. I+ ha
+he new
! cases % + was eval 40une 10 be a
- worse Case, Qnd fef aced,'one l of +he original sixteen . .,
I t
b "
U i!
o l ._Z27 (ItenfihigSidewoPressure Vio,atione R.2 _ guyah x - ...- .~.- -
- .~ a Ed C H m %
...n .ca p - u- z y n PURPOSE I -
'ne' purpass1 is to determine whether maximum
-; sicewall pressures have been exceeded in i conduits with rnul+ipie bends be. tween pu)I poinis.
. Assumpr2 ors
' That the conc'aits chosen were a gocd representation of he wors+ case conditions + hat existed in +he plan +,'
That the measacernents taken in the freld andee drowines mac'e +aerefrorn are on accurate rcresehtation o : +he field installatfors . That alI
( condui+ + fitting openings were utiliz.eo as Jull poin s.-
l REFERENCES
- I
- S.N.P. SM I-O-317-32 "Walkdown procedure for iden+ifyinq sklewall pressure vtala+ ions In conduits wilk mulHple bends in the auxiliary building."%ek.I n3&727 2 Memorandam from'.W.S.Roughley to: Those h'slec .
'~
, subject : Electrical Issues-Caole sideell Pressure l . Tune 23,l9B(o BH38(o042(A3] nm. Awh.2 pg.17 of 727 4 DATA
( c m See affachmen+3 3E 43'NE l32 .190,6E 215 ,
j!. 7E r. 3l 12Epb.70,
=; l30p.40k,14 23o E6Ee.245,9E p
r.2h4,lOEp$,13)
.433,15E r.470, %E p.5 , I7Ep.b71,1 18Ep.6%
Identifyim[Sidewd Preswre Violatiod~R.2 ; aT N
(~ .. -.... - .
. . - . ,u..mD3K n .It-22-E
- . . - - - . - . . . . . . . . - . -% ....tt- u - W C6MPUTATloNS
! ~
See abhments so .so,4Dr.126,5D r.lso,6D e.212, l 7Dp.227, 242 p.255, /ODp .308,IlD p. 326, j 12Dp.363,1 .40ll/h .423,15Dr .459,14Dr .509,17Dr.569, 4
and 18Dp .64 .. .
I Surpontials GRaen cs t See at+achmen+s asp 2e, too,ss r177.ss p210,7sp.221, 88p.240,9Bp.252,108p.307, p.325,128 340,138 .
146pH20,158p.450,I6BpH89,176p.550,and BBp4 SummAny or nesutrs See- at+achmen+3 SA .27,WipM .I .209,
.220,6A >.239,9Ar.2 I,ICAp 306, 24, 339
~
' P Bol, j4[p.4)q ,l5A y.449,16A p.488,I r.549,and 18Ap'.59(o 4
Conccusions al, oF the calculated As shown in the summaries'lliac sidewalI pr essures and pu within the. rescribed aidelines when +he tensions were.
cm>l we encoded to the. prograrn as bein .
pul in +he common sense direckn thai the. g '
craftsmen would hcwe pullec t,em.Of the sixteen cases onl three -failec wxn +he t
were encoded ce, 'ne alled in the non- ommon
. sense direckton ,le.. upt!rd agains+ gravity,etc .
e "L,
t .'
... i .-. - - - _ - - . ...- ....-. .. - - - - . _ ..-. _ .- - ... -
& REVISION LOG EJ 9 rm.dDENTIfYING SIDEWALL PRESSt>RE VIOLATIONS REV2 E -O 5
"'[,.
DESCRIPTION OF REVISION %$ l,',o i
I. This revision replaces -five of the cases with be new cases tha+ previous sixteen II-II-%
better represent the. worst case condi%n. Adds a conduit selecten -
methodology sheet and a memorandum that Sfipulated %e new cable. evaluation criferia. Also calculates each pull twice,ie once pulled in the downward direcflon and once in+he upwarcl.
- 2. This revision clarifies the process di#erences betnieen Rev. O and Rev.l , corrects some computee operafor input errors on one case , cd/s do the qssurnpfions , explains somc~ carnputen prograin Ic9 f c., adds explanations -for the selecfion of the cases considered worst case and lisis page numbers d'or easy reference dF memorandum and cdtachments.
r me Tvaiosuisuoss4 m compttfBr VfK //-29-F6
,\ checksA .9Ltoj tl~PF1g
. .. -