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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:NRC TO UTILITY
MONTHYEARML20062G7711990-11-20020 November 1990 Forwards Computer Printout of Generic & Plant Specific Info Contained in NRC Sims for Facility.Requests That Sims Printout Be Updated W/Actual or Projected Completion Dates for MPA Items within 90 Days of Receipt of Ltr ML20062F5491990-11-16016 November 1990 Forwards Insp Repts 50-327/90-34 & 50-328/90-34 on 901006- 1105 & Notice of Violation ML20217A5461990-11-14014 November 1990 Ack Receipt of 901026 Response to Violations Noted in Insp Repts 50-327/90-28 & 50-328/90-28.Implementation of Corrective Actions Will Be Examined During Future Insp IR 05000327/19900221990-11-13013 November 1990 Ack Receipt of Addl Response to Violations Noted in Insp Repts 50-327/90-22 & 50-328/90-22.Corrective Actions Will Be Examined During Future Insps ML20217A6051990-11-0909 November 1990 Forwards Augmented Insp Team Repts 50-327/90-36 & 50-328/90-36 on 901011-19.NRC Concludes That Multiple Failures of Main Steam Check Valves on 901008 Resulted from Inadequate Recognition & Correction of Deficiencies ML20062F1831990-11-0808 November 1990 Advises That 901015 Rev 25 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20058E1111990-11-0202 November 1990 Grants 901023 Request for Extension of 60-day Reporting Requirement for Cycle 5 Radial Peaking Factor Limit Rept ML20058F1141990-11-0101 November 1990 Forwards Insp Repts 50-327/90-32 & 50-328/90-32 on 900906- 1005 & Notice of Violation IR 05000327/19900181990-10-31031 October 1990 Ack Receipt of Addressing Open Unresolved Items in Insp Repts 50-327/90-18 & 50-328/90-18 ML20058A8441990-10-11011 October 1990 Forwards Insp Repts 50-327/90-29 & 50-328/90-29 on 900827-31 & Notice of Violation ML20062A0611990-10-0909 October 1990 Expresses Appreciation to Util for Prompt and Extensive Support Extended to NRC Following Fire at Inspector Home ML20059N5811990-10-0202 October 1990 Forwards Insp Repts 50-327/90-31 & 50-328/90-31 on 900910-14.No Violations or Deviations Noted ML20059N0711990-10-0202 October 1990 Requests Util to Provide within 45 Days of Receipt of Ltr Listing of All Commitments Made to Justify Restart of Plant IR 05000327/19900231990-09-19019 September 1990 Confirms 900924 Mgt Meeting in Atlanta,Ga to Discuss ALARA Program & Weaknesses Noted in Insp Repts 50-327/90-23 & 50-328/90-23 ML20059F9071990-09-10010 September 1990 Ack Receipt of & Payment of Civil Penalty in Amount of $75,000,per NRC ML20059H3741990-08-31031 August 1990 Forwards Insp Repts 50-327/90-26 & 50-328/90-26 on 900706-0805.Noncited Violations Noted ML20059H0311990-08-30030 August 1990 Forwards Insp Repts 50-327/90-23 & 50-328/90-23 on 900625-29 & 0730.Weaknesses Noted.Util Encouraged to Provide Increased Mgt Attention to Radiological Controls to Assure That Significant Decline in ALARA Program Does Not Occur ML20059H3531990-08-29029 August 1990 Forwards Insp Repts 50-327/90-27 & 50-328/90-27 on 900730-0803.No Violations or Deviations Noted ML20056B4991990-08-21021 August 1990 Forwards Evaluation of Westinghouse Owners Group Bounding Analysis,Per Util Response to Bulletin 88-011, Pressurizer Surge Line Thermal Stratification ML20058P8111990-08-0303 August 1990 Forwards Insp Repts 50-327/90-21 & 50-328/90-21 on 900709-13.No Violations or Deviations Noted ML20056A4751990-07-26026 July 1990 Forwards Insp Repts 50-327/90-22 & 50-328/90-22 on 900606- 0705 & Notice of Violation.Nrc Decided Not to Hold Enforcement Conference or Propose Civil Penalty Because Significant Changes in Plant Mgt Occurred ML20055H9261990-07-25025 July 1990 Advises That 900119 Response to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations, Acceptable ML20055H8851990-07-25025 July 1990 Considers 900425 Request for Approval to Eliminate Site Local Recovery Ctrs Withdrawn.Review Terminated IR 05000327/19900091990-07-20020 July 1990 Discusses SALP Repts 50-327/90-09 & 50-328/90-09 & Forwards Summary of 900530 SALP Meeting.Improvements Noted.Encourages Pursuance & Monitoring of Effectiveness of Corrective Actions ML20055G5651990-07-20020 July 1990 Forwards Order Imposing Civil Penalty in Amount of $75,000, Per 900412 Notice of Violation.Violation Regards RHR Pump Deadheading.Requests Listed Info within 30 Days of Ltr Date ML20055F9181990-07-19019 July 1990 Discusses Corrective Actions for Feedwater Control Problems During Unit 2,Cycle 3 Restart.Nrc Concludes That Feedwater Control Study Addresses Problems of feedwater-related Trips That Occurred in 1988 & 1989 ML20055G3381990-07-18018 July 1990 Advises of Closure of Review of Generic Ltr 83-28,Item 2.2.2 Re Vendor Interface for safety-related Components ML20055F7971990-07-16016 July 1990 Advises That 900126 Response to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment, Acceptable.Documentation Re Implementation of Generic Ltr & Results of Programs Should Be Retained in Plant Records ML20055D8231990-07-0303 July 1990 Advises That Util 890223,0512 & 900204 Responses to Generic Ltr 88-14 Re Instrument Air Sys Acceptable ML20055D2611990-06-29029 June 1990 Requests Addl Info Re Alternative Testing of Reactor Vessel Head & Internals Lifting Rigs ML20055H3901990-06-29029 June 1990 Forwards Insp Repts 50-327/90-20 & 50-328/90-20 on 900506-0606.No Violations or Deviations Noted IR 05000327/19900141990-06-25025 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-327/90-14 & 50-328/90-14 ML20059M8551990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248E2291989-09-28028 September 1989 Requests Addl Info Re Implementation of Suppl 3 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, within 30 Days of Ltr Receipt IR 05000327/19890111989-09-26026 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-327/89-11 & 50-328/89-11 ML20248C1121989-09-22022 September 1989 Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $87,500 from Insp on 890506-0605 ML20248C7361989-09-21021 September 1989 Discusses Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 891211.Encl Ref Matl Requested by 891011 in Order to Meet Schedule ML20247K3121989-09-14014 September 1989 Forwards Safety Evaluation Accepting ATWS Mitigation Sys for Plant.Atws Requirements Under Review to Determine to What Extent Tech Specs Appropriate ML20247N8421989-09-14014 September 1989 Forwards Amend 9 to Indemnity Agreement B-82,reflecting Rev to 10CFR140,increasing Primary Layer of Nuclear Energy Liability Insurance ML20247E6811989-09-0707 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-327/89-17 & 50-328/89-17 ML20247A9981989-08-31031 August 1989 Forwards Insp Repts 50-327/89-14 & 50-328/89-14 on 890424-28 & Notice of Violation.Insp Determined That Plant Personnel Failed to Follow Established Procedures for Assuring Proper Voltage on Shutdown Boards ML20246L0061989-08-29029 August 1989 Advises That Util 890612 Response to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs, Acceptable ML20246P6741989-08-29029 August 1989 Forwards Insp Repts 50-327/89-20 & 50-328/89-20 on 890717-20.No Violations or Deviations Noted ML20246M5791989-08-25025 August 1989 Forwards Insp Repts 50-327/89-19 & 50-328/89-19 on 890706-0805 & Notice of Violation ML20245K2111989-08-17017 August 1989 Confirms 890809 Withdrawal of Application for Permission to Dispose of Low Activity Radwaste in Sanitary Landfill,Per 10CFR20.302 ML20245K4311989-08-10010 August 1989 Forwards Insp Repts 50-327/89-18 & 50-328/89-18 on 890606-0705 & Notice of Violation ML20245K8741989-08-10010 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-327/89-15 & 50-328/89-15 ML20245L3001989-08-0808 August 1989 Forwards Insp Repts 50-327/89-11 & 50-328/89-11 on 890626-30 & Notice of Violation 1990-09-19
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217J4151999-10-15015 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 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 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 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 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 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) 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, ML20211G5881999-08-27027 August 1999 Submits Summary of 990820 Management Meeting Re Plant Performance.List of Attendees & Matl Used in Presentation Enclosed 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 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 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 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 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 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 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 ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML20205T1751999-04-0909 April 1999 Informs That on 990408 R Driscoll & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Dates Scheduled for Wk of 000807 for Approx Seven Candidates ML20205B9601999-03-24024 March 1999 Seventh Partial Response to FOIA Request for Documents. Records in App N Already Available in Pdr.App O Records Being Released in Entirety & App P Records Being Withheld in Part (Ref FOIA Exemptions 7C,2 & 5) ML20204J5451999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Sequoyah Plant Performance Review on Feb 1998-Jan 1999.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl ML20204J5721999-03-15015 March 1999 Forwards Insp Repts 50-327/99-01 & 50-328/99-01 on 990103-0213.Violations Noted & Being Treated as non-cited Violations.Weakness Identified in Licensed Operator Training Program & Freeze Protection Program ML20207J0901999-03-0303 March 1999 Forwards FEMA Final Rept for 981104-05,full Participation, Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans for Sequoyah Npp.Three Areas Requiring Corrective Action Identified ML20203H7211999-02-18018 February 1999 Forwards Safety Evaluation Accepting Topical Rept BAW-2328, Blended Uranium Lead Test Assembly Design Rept, for Allowing Insertion of Lead Test Assemblies in Plant,Unit 2 Cycle 10 Core.Rept Acceptable with Listed Conditions ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20203G5631999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20202J1211999-02-0202 February 1999 Submits Summary of 990128 Meeting with Listed Attendees at Region II Ofc for Presentation of Recent Plant Performance. Presentation Handout Encl ML20202J5421999-02-0101 February 1999 Forwards Insp Repts 50-327/98-11 & 50-328/98-11 on 981122-990102 & Nov.Violations Noted Re Failure to Comply with EOPs Following Rt & Failure to Enter TS 3.0.3 When Limiting Condition for RCS Flow Instrumentation TS Not Met ML20202C1771999-01-27027 January 1999 Forwards Request for Addl Info Re Util 980428 Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Licensee Agreed to Provide Response to Request by 990426 ML20199E7081998-12-23023 December 1998 Refers to 991105 Training Managers Conference Conducted at RB Russel Bldg.Agenda Used for Training Conference & List of Attendees Encl.Goal of Providing Open Forum for Discussion of Operator Licensing Issues Was Met IR 05000327/19980151998-12-17017 December 1998 Forwards Safeguards Insp Repts 50-327/98-15 & 50-328/98-15 on 981116-20.No Violations or Deviations Noted.Repts Withheld Per 10CFR73.21 ML20198A8101998-12-0707 December 1998 Forwards Insp Repts 50-327/98-10 & 50-328/98-10 on 981011- 1121.No Violations Noted ML20206N4171998-12-0404 December 1998 Forwards Insp Repts 50-327/98-14 & 50-328/98-14 on 981102-06.No Violations Noted.Insp Team Observed Selected Portions of Emergency Organization Response in Key Facilities During EP Plume Exposure Exercise on 981104 ML20198A8531998-12-0404 December 1998 Expresses Appreciation for Support That TVA Provided NRC During Recent Plant Emergency Exercise.All Foreign Vistors Expressed Appreciation for Very Informative & Interesting Visit to TVA ML20196D6001998-11-24024 November 1998 Forwards Insp Repts 50-327/98-13 & 50-328/98-13 on 980914- 1016 & Notice of Violation Re Lack of Attention to Detail Installing Unit 2 Intermediate Deck Doors ML20196C5191998-11-17017 November 1998 Confirms 981110 Telephone Conversation Between P Salas & H Christensen Re Mgt Meeting Which Has Been Scehduled for 990128.The Purpose of Meeting Will Be to Discuss Recent Plant Performance for Sequoyah ML20196D0831998-11-16016 November 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting Held on 981102.Details of Insp Plan Through March 1999 & Historical Listing of Plant Issues,Called Plant Issues Matrix,Encl ML20196D5981998-11-13013 November 1998 Informs That on 981007,NRC Administered Gfes of Written Operator Licensing Examination.Copy of Answer Key & Master Bwr/Pwr GFE Encl,Even Though Facility Did Not Participate in Exam.Without Encl ML20196D4121998-11-13013 November 1998 Discusses 981110 Request Re Noed.Based on NRC Evaluation, Staff Concluded That NOED Warranted.Nrc Intends to Exercise Discretion Not to Enforce Compliance with TS 3.8.2.1,action B,For Period from 981110-12,at Stated Times ML20195G5331998-11-0909 November 1998 Forwards Insp Repts 50-327/98-09 & 50-328/98-09 on 980830-1010 & NOV Re Failure to Perform Adequate Testing to Ensure That Low Voltage Circuit Breakers Would Perform Satisfactorily in Svc ML20207M6951998-10-30030 October 1998 Informs That on 980928-1001 NRC Administered Operating Exam to Employees Applying for Licenses to Operate at Plant ML20155A5131998-10-22022 October 1998 Discusses Review of Response to GL 97-05 for Plant,Units 1 & 2.Review Did Not Identify Any Concerns with SG Tube Insp Techniques ML20155B7481998-10-0909 October 1998 Extends Invitation to Attend Training Manager Conference on 981105 in Atlanta,Ga.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Affect Licensing of Reactor Plant Operators ML20154D3081998-09-18018 September 1998 Forwards Insp Repts 50-327/98-08 & 50-328/98-08 on 980719- 0829.No Violations Noted.Effective Radiological Emergency Plan Drill Was Conducted ML20239A0601998-08-27027 August 1998 Forwards SER Re Licensee 960213,0315 & 0806 Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Staff Finds Licensee Adequately Addressed Actions Requested in GL 95-07 1999-09-07
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Docketflos.: 50-327 ,..
and 50-328 3 3 JAN iS87 ifr. S. A. White fianager of Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
Subject:
Transmittal of Draft Safety Evaluation on Brarch Technical Position PSB-1 The staff has prepared the enclosed draft safety evaluation on the Tennessee Valley Authority (TVA) Branch Technical Position (BTP) PSB-1.
The staf f intends to incorporate this evaluation into the Safety Evaluation Report (SER) on Volume 2 of the Nuclear Performance Plan which addresses Sequoyah.
Based on its review, the staff has found the TVA response to BTP PSB-1 acceptable. You shculd assure that any safety-related employee concerns pertaining to this issue ere appropriately addressed prior to the start-up of the Sequcyah units.
If you have any questions, please contact the Sequoyah Project f'anager, Mr. Joseph Holonich at (301) 492-7270.
Sincerely,d\
B. J. Youngbicod, Director
- PWR Project Directorate #4 Division of PWR Licensing-A
Enclosure:
As stated
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Mr. S. A. White Tennessee Valley Authority Sequoyah Nuclear Plant cc:
Tennessee Department of Public Regional Administrator, Peofon Ti Health ATTN: Director, Rureau of U.S. Nuclear Regulatory Commission, 101 Ma rietta Street, N.W., Suite 2900 Environmental Health Services Atlanta, Georgia 30323 Cordell Hull Building Nashville, Tennessee 37?l9 J.A. Kirkebo ATTN: D.L. Williams Mr. Michael H. Mobley, Director Tennessee Valley Authority Division of Radiological Health 400 West Summit Hill Drive, W12 Al? T.E.R.R.A. Buildiro Knoxville, Tennessee 37902 150 4th Avenue North Nashville, Tennessee 37203 Mr. Bob Faas Westinghouse Electric Corp. County Judge -
P.O. Box 355 Hamilton County tourtheuse Pittsburgh, Pennsylvania 15230 Chattanooga, Tennassee 37402 R. L. Gridley Tennessee Valley Autnority SN 1578 Lookout Place Chattanooga, Tennessee 3740?-7801 M. R. Harding Tennessee Valley Authority Seouoyah Nuclear Plant P.O. Box 2000 Soddy Daisy, Tennessee 37379 Resident Inspector /Sequoyah NPS c/o U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 H.L. Abercrombie Tennessee Valley Authority Seouoyah Nuclear Plant P.O. Box 2000 Soddy Daisy, Tennessee 37379
, 4.1 Pranch Technical Position PSR-1 4.1.1 Summary of issue in order to verify the validity of voltage drop calculations for the Sequovah Nuclear Plant Auxiliary Power System (APS), the staff recommended by letter dated March 26, 1986 that TVA perform a new verification test es prescribed in Branch Technical Position PSB-1 (part B.4) since the staff could not conclude that TVA had adequately demonstrated that a new verification test was not I
necessary. This recommendation was largely based on the staff's review of TVA's October 2,1980 test report and finding of inconsistency in load valves used in the analysis with what was secured during the test. Also, there have been chances in the APS configuration and the computer procrams used for the above voltage drop calculations. A meeting was held on April 16, 1986, during which TVA presented additional infomation and clarification to their October i
2, 1980 test report in support of its position that performina additional verification testing of the APS at Sequoyah was not necessary. Subsecuently, TVA agreed to provide additional information for further staff review as follows:
- 1) Confirmatory analysis to demonstrate that the new computer procram is com-parable to the old computer procram which was used in the original test report by inputting the same load values into the new computer program and comparing the calculated voltages.
- 2) Analyses to demonstrate that there is no significant configuration change between the 1980 and 1986 systems by inputting the data from the July 12 and 16, 1980 tests into the 1980 A 1996 system models and comparino the calculated voltages.
- 3) More detail on how the two tests (.luly 19 and 16,1980) were conducted and description of how the circuit breakers were aligned for each configuration.
- On June ?,1986, TVA provided a response along with a report titled "NRC Branch Technical Position PSR-1 Reanalysis."
The staff has reviewed the additional information and has re-evaluated the previous position on the need for the verification test.
However, the staff still could not conclude that sufficient basis was provided to demonstrate that no new verification test was necessary since the computer program could not predict the transient response of the system. The staff transmitted its evaluation expressing this conclusion to TVA by letter dated August 1,1086 and also transmitted additional questions requiring further clarification on the transient analysis on August 7,1986. Ry letter dated September 11, 1986, TVA provided their response to these ouestions, and aua-mented this response by letter dated December 3, 1086. The staff has reviewed the information provided by TVA on the need for verification testing. Its evaluation is presented below.
4.1.? Evaluation 4.1.2.1 Computer Hardware and Program Changes Since the mainframe computer (MC) and its program "VNEW" which were used for the previous verification test have been replaced by the personal computer (PC) with a new program called " RADIAL", the staff was concerned whether the proaram l
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W RADIAL /PC is equivalent to the old program VNEW/MC regarding analytical tech-niques and assumptions. At the April 16, 1986 meeting, the staff requested a confirmatory analysis using the July 12, 1980 test configuration to demonstrate that there is no appreciable difference in the calculated voltages of the two (i.e., RADIAL /PC vs. VNEW/MC). TVA also included a Stone & Webster computer program. All three computer programs were run by using an identical set of loads for each board. The results were as follows BOARD VNEW RADIAL STONE & WEBSTER 6.9 kV Start BUS A 7152 7151 7148 6.9 kV Start BUS B 7011 7008 7005 6.9 kV Unit Bd IB 7011 7008 7005 6.9 kV Shutdown Bd 1A-A 7004 7002 6998 480 V Shutdown Bd 1Al-A 495 495 495 480 V RX Vent Bd 1A-A 483 483 Not Conducted The staff review of the results of these analyses finds that the voltage . values obtained from the three computer programs show no appreciable voltage dif-ferences. Consequently, this indicates that both computer programs' analytical techniques and assumptions are equivalent for the steady state. However, this comparison requires verification of the steady state and transient response characteristics of the two computer programs. This test result failed to demonstrate the transient response and the steady state at 120/208 volt level.
Therefore, the replacement of the old computer program with the new computer program appears to be verified for the steady state case only down to the 480 volt level.
In the evaluation transmitted to TVA by its August 1,1986 letter, the staff requested additional justification for not performing the PSB-1 test down to the 120/208 V level. TVA responsed to this issue by describing their two 120 V ac control power systems as follows: one is the 120V ac Vital Instrumentation and Control Power System (VCPS) fed from the vital inverters and the other con-sists of Class 1E 120 V ac Motor Control Centers (MCCs) supplied from the 480/120 V control power transformers. For the 120 V ac VCPS, the vital inverters are designed to maintain the output voltage regulation within 2% of 120 V ac with an input voltage of 480 V ac 7.5%. In addition, upon loss for unacceptable degradation) of the 480 V ac input, the battery will supply the loads with no interruption of regulated power. For the Class IE 120 V ac PCCs, TVA referred to their recent transient voltage calculations which were performed under worst-case conditions (i.e., the worst expected transient voltage at each MCC) to demonstrate that adequate voltage exists to pick up the control devices (i.e., motor starter, solenoids, relays, etc.) for expected transient conditions.
The staff review has found that TVA's new computer program can adequately predict the response of the Sequoyah power system down to the 480 V level, the VCPS through its inverter and battery backup design eliminates the effects from 480 V ac degraded voltage input or transients, and the worst case transient calcula-tions indicate that the 480/120 V ac MCC control power transformers can ade-quately perform their safety functions.
The staff concurs with the TVA assessment that the 120 V ac VCPS design features and the voltage calculations performed for the worst case 120 V ac MCC voltages assure that adequate voltage will be available to components supplied by the 120 V ac control power system. Thus, no additional PSB-1 related tests to demonstrate system response at the 120/208 V level are necessary.
1.1.2.2 Change Out of 100 Valve Motors Another concern identified by the staff was that the replacement of 100 valve notors with the motors of different electrical characteristics rey affect the plant steady state load making it necessary for the new system loadings to be re-analyzed. However, TVA indicated that this charge out will only affect the transient loading and voltage whereas the steady state load remains the same.
Therefore, the staff finds that the change out of 100 valve n.cters represents no overall load increase for the steady state ccr.dition.
4.1.2.3 Addition of Two Start Buses and One Comn,on Station Service Transformer In response to a staff concern that TVA had added two nce stert buses which could result in new loads or impedance, TVA explained that the two additional start buses were not actually added, but instead, the original two start buses were split into four buses, thus no new loads or impedances woulo be added.
Although the third common' station service transformer has been added, the cir-cuit breakers are normally open making the transformer available as a backup for either of the other stetion service transformers. TVA den.onstrated that ,
this change has little effect on the overall Sequoyah APS cor. figuration by performing a comparison of the voltage analyses between the 1980 (two start FLses) and 1986 (four start buses) configurations. The compariser was perforried Usino the July 12 and 16, 1980 test data and the new computer progran. TFr results are summarized as follows:
TEST I TEST II (July 12, 1980) (July 16, 1980) t CONFIGURATION CONFIGURATION BOARD 1980 1986 1980 1986 F.TTV Start EUS A 7T5T 7135 70T5 7DTI 6.9 kV Start BUS B 7051 7045 7067 7062 6.9 kV Unit Bd IB 7051 7045 7067 7062 6.9 kV Shutdown Bd 1A-A 7044 7038 7060 7055 4F0 V Shutdown Bd 1Al-A 501 500 501 501 4E0 V RX Vent Bd 1A-A 493 500 494 501 Start of EPCW pp (Tern. V) Not Conducteo C705 6695 Start of Aux. BLG E)H f/fl 1A Not Conducted 495 458 As can be seen for the above results the analyses show oc appreciable voltage difference (max.1.5%) betweer the 1900 and 1986 configurations. Therefcre, this incicates that the new configuration has not changed the old electrical syster configuration significantly.
4.1.2.4 Reanalysis of the 1900 Verification Test Results With respect to the verification tests performed at Sequoyah in 19P0, TV/., in its June 2, 1986 response, explained how the circuit breakers were aligred fer each test configuration.
The staf f review of the test procedure found that a comparison was madt Letween the calculated board voltages, based on load values derived (not neasured) f ron
, -4_
breaker alignment and the supply voltages, and the board voltages cbtained from the tests. The staff found that this procedure deviated from our Branch Technical Position PSB-1 (Part B.4) which requires measurements of bcth leads and voltages for a given test configuration and then, using the, raeasurer' icad values on each board as input to the computer model to calculate the voltages.
Subsequently, the analytically derived voltage values and the test results are compa red. To be consistent with our present PSB-1 procedure, during the meeting on April 16, 1986, the staff requested new analyses be performed by using the load values obtaired during the tests as input to the new computer pregr6m. The results are as follows:
TEST I TEST II (July 12, 1980) (July 16, 1980)
BOARD PEASURED ANALYSIS % MEASURED ANALYSIS 7 T.T IV Start BUS A 7200 7154 D.6 7000 7045 V.6 6.9 kV Start BUS B 7000 7051 0.7 7000 7067 1.0 6.9 kV Unit Bd IB 7100 7051 0.7 7090 7067 0.3 6.9 kV Shutdown Bd 1A-A 7000 7044 0.6 7100 7060 0.6 4P0 V Shetdchn Bd IAl-A 495 501 1.2 500 501 0.2 480 V RX Vent Bd 1A-A 404 493 1.9 489 494 1.0 Start of ERCW pp Not Ccrducted 6787 6705 1.2 (Tem V)
Start of AUX. BLG Not Conducted 466 450 1.F EXP FAN 1A TVA used board meters, test meters and brush recorders for taking test measure-rents. However, due to calibrction prublems the brush recorcer failed to yield consistent results. As a result, TVA's Jure ?, 1986 response did not include the measured values obtained from the brush recorder. It is also indicated that current transfonner and pcwcr transformer inaccuracies were present.
Because the allched accuracy limit was not specified by the staff in Position 4 of FSAR Question 0.33, TVA stated that all measurements were taken by the board neters whose accuracy was limited to 5%. Therefore, a 5% tclerance was estab-lished cs the raximum acceotable difference between the measured voltages ari calculated voltages.
4.1.2.5 Branch Technical Position PSB-1 (PART E.a)
TVA perferred the 1980 verification tests at Sequoyah in response to a staff ouestion which was askcd during the licensing review (FSAR Ouestien 8.33).
i This questier was a precursor to Branch Technical Position PSB-1 (Part B.4) which was issued as part of the Standard Review Plan ir Jnly 1981. Part B.4 of PSB-1 provides detailed guidance for perfonnance of their verificction tests.
Although Question 8.33 does not explicitly foclude all of the guidance of Part B.4 of PSB-1, it does so by clear implication. Therefore, the staff evaluation of the 1980 tests was based cr. establishing a correlation between these tests and the testing and expected test rcsults specified in Part B.4 of PSB-1. In the April 16, 1900 meeting, TVA concurred that the intent of posi-tion 4 of (uestion E.33 requirement is the sare as Part E.4 of PSC-1 require-ments, even though the PSB-1 requirements are Fore specific.
I Part B.4 of PSB-1 states the following:
a) leadfep the station distribution buses, including all Class IE buses dct.n to the 120/208 Y level, to at least 307; _.
b) recording to the existing grid crd Class IE bus voltages and bus loeding ocwn the 120/208 volt level at steady conditiers and during the starting of both a large Class IE and ncn-Class IE motor (not concurrently);
hote:
to rainilaize the number of instrumented locations, (recorders) during the motor starting transiert tests, the bus voltages and Iceding need only be recorded on thet string of buses which previously showed the lowest analyzed voltages.
c) usir.g the analytical techniques and assumptions of the previous vcltage erelyses and the measured existing grid voltage and bus loading conditicrs recorded during conduct of the test, calculate new set of voltages for all the Class IE buses down tc the 120/E08 volt level; d) compare the analytically derived voltage values agairst tFe test results.
L'ith sced ccrrelation (within 37) between the analytical results and the test results, is tre validity of the mathervatical model used in the voltage arelysis established. However, the above procedure involves testing c' teth the steady state erd trcnsient response characteristics. In order to perfom the transient motor testing, the starting of both a large class 1E erd ncn-class IE is required.
The intent of such a transient test reccirerrent is to detect potential spuricus loaa sheocing motor is started.or separation of class IE system fren offsite power when a large The ability of the computer rodel to predict the effects of the motor transient in the systen is verified by cortparirr tFe data raeasured duririg the trenstent test with the computer predicted transient values. Upon ccrplction of both the steady state and transient analyses, the validity cf the tretherratical model is verified.
Lased on its review of the June 2, IcF6 submittal, the staff has concluded that there is reasoneble assurance that TVA's new ccrputer program can adequately predict Sequoyah /.PS steady-state response characteristics. However, the staff made the following firidir.gs en the transient aspect of the PFP 1 test.
1.
The test report indicated instrurrent recording problems such that starting retor dip values were not reliably estchlished (i.e., no transiert dett for the motor and the class IE busts).
1.
The selected r.otor sizes (700 hp are 1EO hp) were not large enough to shu.
cr,y significant transient effect (the dip was only for one cycle). The Erarich Technical position PSE-1 (pert B.4) requires starting of both 4.
large class 1E and a large non-class if irotor (not concurrently).
2.
L'o transient voltage analysis wet perforried by comparing resuits ei cM-culations performed by the new corputer program with the data obtained during the starting of large trators.
Subsequent to the staff's August 1,1986 evaluation, the staff transnitted a request for additional information covering the transient aspects of the PSC-1 test. Cr September 11, 1986, TVA provided its response to the questions and further augmented this response by letter dated Decernber 3,1986.
In the absence of an explanation regarding the transient measurements taken curing the starting of large n:cters and how these values were used to assure the computer model's ability to accurately predict trensient effects, TVA pro-vided the brush recorder traces (voltage and currer.t) taken at the motor tenainals for the 460 Y Auxiliary Building General Supply UFCS) fan and the largest f.f kV Essential Raw Cooling Water (EfCk) pump on the 6.9 kV shutdown beard. The measured voltage values for the equipment have been cerrpered with theold(VNEW)andnew(RADIAL /1900and1966 configuration)voltagevalves calculated fron the computer programs.
MEASURED CALCULATED VOLTAGES H.P. VOLTAGE VNEW RADIAL (80) RADIAL (86) DIFF (%)
ERCW Pump 7F 6787 M7 6703 6695 1.4 ABGS Fan 150 466 449 459 45E 3.8 TVA found the maximum deviation to be 3.8r between the measured voltage ar.d the voltege calculated using the old program (VNEl.') with loading derived fror the closed circuit breaker configuration and individual load ratings. The deviation in this case is more than the 3% guideline described in PSE-1. However, the measured voltages when compared with the new corcuter program voltages derived using r.easured bus load values were within 2%. Therefore, the staff concluces that TVA's new con.puter model can accurately predict the transient respor.se cf the system.
With respect to the request to " provide the brush recorder traces of load currents obtained during the ncter starting transient tests whicF were used in the transient calculatinns perforr.ed of ter the test to predict systen tus volteges," TVA provided the measureo startirs and running currents for pbese A and C of the 6.6 kV ERCW punp and 460 V ABGS fan. Although the brush reccrder traces incleted both the voltage and current neasurercents, the main focus of PSB-1 deals only with the voltages available in the C1tss IF buses. Therefore ,
the measured current values were not used to calculate bus voltages, but pro-vided to show the actual length of the notor startine transient as oppcsed to the voltage traces which changed very little due to the stiffness of the ptwer source. However, the measured nFese A starting currents were used to calculate the first-cycle voltage dips which were compared with the measured voltage values. The two results were found to be the sane.
Curing its review of these recordings, the staff found a difference in the phase A ana phase C running current values which could be indicative of a phase unbalance condition or a rneter abnormality. In addition, these un-balancec current values, if used, pctertially could affect the system bus voltage calculations.
By letter dated December 3, 1986, TVA explained that the differences in the Otasc A and C current readings are nut indicative of a phase current unbeler.cc, but are due to instrument calibration problems. The fact that no real crbelance
between phase A and C existed was substantiated by a corrperison of the board instrumentation reters reasbring the same currents. I.e., the board meter readings indicated no substantial difference in chase A and C currents.
~
The staff has reviewed the reccrdings of the voltage traces and finds then con-sistent with the licensee's discussion of the trotor transients. Thereforc, the staf f concurs with TVA that no actual unbalance of rctor phase currents existeo and that the voltage traces are adecuate for the PSB-1 analysis.
To accress the one cycle voltage dip experierccd during the motor starting transient test, TVA provided the brush recorder traces of the terrrinal voltage and current for the 6.6 kV ERCW pump and 460 V ABGS fan which they obtained during the tactor transient tests. The current traces clearly indicated that the acceleration times were about one second for the ERCW pump ard about seven socords for the ABGS fan. TVA determined from the voltage traces that the 6.6 kV ERCW purap motor start dio depress the teminal voltage for approyirately the acceleration tirae (i.e. , 60 cycles). However, the measured voltage die for the 460 V APGS fan was for only approximately 6 cycles. For both cases, the worst part of the voltage dip occurred during the first cycle. TVA, further, concluded that this ccrresponds to the instant that the rnotor rotor is locked and the reter just starts to accelerate. TVA further stated that there was no reasurable voltage sag at either the 6.9 kV or the 480 V switchgear buses during rcctor start.
Based on its review of TVA's brush recorder traces, the staff finds the TVA assessrcent of the Dotor starting voltage transients acceDtable.
In regard to an additional staff concern of whether conservatism was used in calculating the ettects of starting large motors, TVA stated "Our analyses are not a true transient calculation which would show the exponential voltage rccovery due to the change in n.otcr incdance while accelerating. Der clicula-tiers essume that the voltage dip is at its lowest Doint for the entire accel-eration tire of the motor." Further, TVA stated " cur transient analyses model the 6.9 kV shutdown beard voltage depressed at the I cycle voltace for the entire acceleration time of the 6.6 kV required starting loads."
The staff finds that the TVA transient analysis model represents a rore con-servative condition with respect to the motor starting vcitage and its duration for the voltage recovery time. Therefore, it concludes that the TVA method for c61culating the effects of startirg large rcotors results in a more conservative transient voltage calculation ther the exponential voltage recovery which actually occurs during rnotor acceleration.
In response to e staff request for the worst case voltage calculation on Class 1E boards duriro the starting of a reactor coolant purcp follcwing an acci-
, dent, TVA deterrnineo the worst case for the 6.9 kV Class IE shutdown boards te be. approximately two minutes after e safety injection and phase B contair,rtrt isolation with the 161-kV grid at a rinimum of 159 kV. Although the voltage at the 6.9 kV Class IE boards dipped to 6761 V upon starting the 6000 hp reactor coolant pump, TVA stated that the board recovered to 690? Y ef ter 6pptoximately 14 seconds. Further, IVA stated that this voltage transient dces r.ot drop out the 6.9 kV Clast IE shutdown boards degraded voltus e relays and adequate vcitage wct1d be available for Class IE leads.
i
. o
,8 -
1 The staff has reviewed this assessment and concludes that the Sequoyah APS is capable of successfully starting a reactor coolant pump following an accident under minimum grid voltane without adversely affecting Class JE loads.
4.1.3 Findings For the steady state aspect of the test, the staff finds that:
1.
The new configuration has not affected the overall voltage profile of the 6.9 kV boards.
2.
The change out of 100 valve motors represent no overall load increase.
3.
The replacement appears of the old computer program with the new computer program to be acceptable.
4 '
Despite the fact that our Position 4 of Question 8.33 contained no specific the consistency 5',
Seouoyah metering was of the results between the anal-accuracy req yses and test values (within ?%) show that the model consistently predicts steady state system performance.
5.,
Although no test and analyses were perfomed down to 170/70R volt level where ability of the class 1E control circuit to pick up the control devices such as starter, relay, and solenoid is determined, TVA has demonstrated that adequate control voltage is available to components supplied by the 120 V ac processing.
Therefore, no additional test are necessary.
As for the transient aspect of the test, the staff finds that:
1.
based on its evaluation of the TVA ,fustification regarding 170 V ac control power system design features and calculations, no additional PSB-1 related transient tests for the 120/708 y level are necessary; 2.
based on its review of the brush recorder voltage and current measurements taken at the terminals of the ERCW and ARGS motors and the supporting information provided by TVA, (1) the differences between the calculated transient voltages from the new computer pro voltages are within the PSR-1 guideline, (2) gram the and onethe measured cycle voltaae transient dip is an accurate measure of the actual minimum transient volta difference in recorded currents (between phases A and C) ge, andto(31 is due a the recorder calibration problem and is not indicative of a current unbalance problem; 3.
in comparison with the exponential voltace recovery model nomally used in calculating the effects of starting large motors, TVA's transient analysis model, which assumes the voltace dip at its lowest point for the entire accelerating time of the motor, is conservative; and 4.
TVA has provided the worst case calculation for voltages on Class IE buses and found pump that an following theaccident.
APS is capable of successfully starting a reactor coolant
, 9 4.1.4 Conclusion Based on its review of the steady-state and the transient calculations provided by TVA, the st4t f ccccludes that there is sufficiert tasis for..TVA's new computer progran to predict the transient and the sitccy-state responses of the
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Sec;uoyah APS. Thus, a new verit1cetion test for the APS voltace study ur. der PSB-1 is not required.
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