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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 PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA
MONTHYEARML20245J7001989-08-0404 August 1989 Forwards Public Notice for Plant for Publication in 890808 Chattanooga New-Free Press & Chattanooga Times.Advertising Order Approving Publication Also Encl ML20245D1911989-06-19019 June 1989 Forwards Public Notice Re Util 890616 Application for Amends for Licenses DPR-77 & DPR-79,revising Spec Re Position Indication sys-operating.Requests Publication in Chattanooga News-Free Press & Chattanooga Times on 890621 ML20245B3881989-06-15015 June 1989 Responds to Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels.Util Actions Do Not Have Adverse Impact on Nuclear Reactor Safety to Extent That Protection of Safety of Environ Affected ML20248B4001989-06-0101 June 1989 Responds to to Chairman Zech Re Articles from Chattanooga News-Free Press.Nrc Conducting Extensive Program of Surveillance & Operations at Facility,Including Evaluations of Allegations Made About Plant Operation ML20245B4051989-04-14014 April 1989 Responds to 881004 & 890119,23 & 0310 Ltrs Re Status of Investigation of Concerns About Corrosion Inhibitors & Design of Sampling Sys.Low Velocity of Liquid in Hotwell Sampling Considered Satisfactory ML20206H4511988-11-0808 November 1988 Final Response to FOIA Request for Documents.Forwards App U Documents.App U Documents Also Available in Pdr.App U Document Withheld (Ref FOIA Exemption 5) DD-88-12, Advises That Time Provided by NRC Regulation for Commission to Review Director'S Decision DD-88-12 Expired.Commission Declined Review & Decision Became Final Agency Action on 880829.Served on 8809071988-09-0707 September 1988 Advises That Time Provided by NRC Regulation for Commission to Review Director'S Decision DD-88-12 Expired.Commission Declined Review & Decision Became Final Agency Action on 880829.Served on 880907 ML20207H8251988-08-25025 August 1988 Forwards Staff Response to to J Keppler Re Comments on TVA Proposed Cable Test Program ML20151Z1421988-08-16016 August 1988 Forwards Response to Stated Ltrs Re Diesel Generator Inadequacies,Used by Petitioners to Request Emergency Suspension of Full Power Operation Pending Completion of Remedial Action.Petition Denied.Encls in Central Files ML20151M6061988-04-19019 April 1988 Responds to FOIA Request for Info Re Scores of Reactor Operators & Senior Reactor Operators.Forwards Requalification Exam Summary Source Sheets Listed in Encl App W/Personal Privacy Info Deleted ML20148K6521988-03-28028 March 1988 Denies 880324 Request for Emergency Relief.Remainder of Request Will Be Treated as Petition for Enforcement Action Under 10CFR2.206 & Will Issue Director'S Decision Shortly. Ltr Raised No New Issues Not Already Considered by NRC IA-87-530, Final Response to FOIA Request for Documents Re Facility. Document Identified in App a Withheld in Entirety (Ref FOIA Exemption 7)1987-08-27027 August 1987 Final Response to FOIA Request for Documents Re Facility. Document Identified in App a Withheld in Entirety (Ref FOIA Exemption 7) ML20238B2571987-08-27027 August 1987 Final Response to FOIA Request for Documents Re Facility. Document Identified in App a Withheld in Entirety (Ref FOIA Exemption 7) ML20211A0661986-10-0303 October 1986 Partial Response to FOIA Request.Forwards Document Listed in App.Document Also Available in PDR ML20205E4481986-08-0808 August 1986 Final Response to FOIA Request.App D Documents Re IE Info Notices,Lers & Insp Repts Placed in PDR IA-85-706, Final Response to FOIA Request.App D Documents Re IE Info Notices,Lers & Insp Repts Placed in PDR1986-08-0808 August 1986 Final Response to FOIA Request.App D Documents Re IE Info Notices,Lers & Insp Repts Placed in PDR ML20203H1741986-07-28028 July 1986 Final Response to FOIA Request.Forwards Documents Listed in App B.App a & B Documents Available in PDR ML20210R5541986-04-17017 April 1986 Partial Response to FOIA Request for Records Indicating Identification & Status of Issues Decided by Notation Vote During Jan-May 1985.App a Documents Available in Pdr.App B Documents Partially Withheld (Ref FOIA Exemption 5) ML20199E5951986-01-30030 January 1986 Further Response to FOIA Request for NRC Response to J Dingell & NRC Ltrs to TVA During 851030-1206. Forwards App B Document.Apps B & C Documents Available in Pdr.W/O Stated Computer Printouts of Ltrs IA-85-813, Further Response to FOIA Request for NRC Response to J Dingell 851118 Ltr & NRC Ltrs to TVA During 851030-1206. Forwards App B Document.Apps B & C Documents Available in Pdr.W/O Stated Computer Printouts of Ltrs1986-01-30030 January 1986 Further Response to FOIA Request for NRC Response to J Dingell 851118 Ltr & NRC Ltrs to TVA During 851030-1206. Forwards App B Document.Apps B & C Documents Available in Pdr.W/O Stated Computer Printouts of Ltrs IA-85-457, Responds to Request for Documents Referenced in NUREG-1037, Containment Performance Working Group Rept. App Documents Available in Pdr.Documents F & G Available for Purchase at NTIS & Gpo1985-07-24024 July 1985 Responds to Request for Documents Referenced in NUREG-1037, Containment Performance Working Group Rept. App Documents Available in Pdr.Documents F & G Available for Purchase at NTIS & Gpo ML20134E1451985-07-24024 July 1985 Responds to Request for Documents Referenced in NUREG-1037, Containment Performance Working Group Rept. App Documents Available in Pdr.Documents F & G Available for Purchase at NTIS & Gpo ML20126E6161985-03-11011 March 1985 Responds to FOIA Request for Source Term Event Trees Prepared by Sandia for Subj Plants.Forwards Documents Listed on App.Documents Also Available in PDR 1989-08-04
[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
[Table view] |
Text
. ,
AUG 2 51988 Docket Nos. 50 327/328 Mr. Dallas R. Hicks 6621 Wachese Lane '
Knoxville, Tennessee 37912
Dear Mr. Hicks:
Reference:
Your letter to James Keppler dated August- 21,1987, "Corinents -
on TVA's Proposed Cable Test Program dated July 31, 1987" Enclosed is the reply of our staff to your letter referenced above. If you have any further cuestions on this subject, please contact Paul Cortland at(301)492-0754 or myself at (301) 492-3288.
Sincerely.
Original Signed by Steven D. Richardson Steven D. Richardson, Director TVA Projects Division Office of Special Projects
Enclosure:
As stated D . DISTRIBUTION:,
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- See previous concurrence if OFC :TVA:TP:EB :TVA:TP: ROB :TVA: ROB /Br :TVA:AD/TP :05P:* A:D : :
NAME :PCortlandiam:HGarg* :EMarinos* :BDLiaw* : sri son : :
DATE :8/ 25/88 :8/ '25/88 :8/25 /88 :8/ 25/88 :8/t</88 : :
OFFICIAL RECORD COPY
RESPONSE TO MR. DALLAS R. HICKS' LETTER DATED AUGUST 21, 1987 "COMMENTS ON TVA'S PROPOSED CABLE TEST PROGRAM, DATED JULY 31, 1988"_
Mr. Hicks comented on TVA letter, R. Gridley to NRC, "Sequoyah Nuclear Plant Units 1 and 2 - Revised Test Program," dated July 31, 1987.
MR. HICKS' "COMMENT NO. 1" TVA stated in page 2. paragraph 2, "In particular, it was apparent that the test voltages utilized were higher than necessary to verify the integrity of the cable. In addition, this testing, which was performed without the introduction of water, was able to detect damage that was insignificant when compared with the type of damage postulated in the technical evaluation report (TER) for pullbys and jaming. Previously, it has been inferred that such damage could be detected by DC high potential testing only in the presence of water."
Mr. Hicks stated that he does not agree "that the test voltages were igher than necessary to verify the integrity of the cable. It just happt +at the <
insulation was already degraded to a level such that lower level of tages ,
could have possibly detected the damage. TVA's statements concerning the '
voltage level and the lack of use of water are misleading and are apparent attempts to justify a position not to use sufficiently high voltages and water imersion of cables as has been recognized as a need for qualification and required by the industry. The fact that a cable insulation fails at a lower voltage and without water is absolutely no reason or justification to lower the voltage and to eliminate water i mersion. Other cable insulations may be unacceptable in integrity of insulation capability but at higher integrity than 4
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- that of the subject failed cables. They would be detected by the conditions of higher voltage and water imersion."
STAFF RESP 0t!SE TO COMMENT NO. 1 The staff has determined that the proposed test voltage of 240 volts DC/ mil based on the minimum qualified thickness of cable is a reasonable test voltage for determining the gross damage to the cable. If a cable has been environmentally qualified for a certain insulation thickness and TVA is using :
a cable with higher insulation thickness, it is unnecessary to require a Hi-Pot test based on the higher thickness. Applying the test voltage based on the minimum qualified thickness will provide assurar.ce that the cable has I not degraded beyond a certain threshold. TVA has tested cable under both wet l and dry conditions.
ftR. HICKS' "COMMENT NO. 2".
TVA stated in page 2, para' graph 3. "As a result of the above, TVA concluded j that continued testing, conducted at the original parameters, coulo potentially impact plant safety and, furtherr:cre, could result in the replacement of acceptable cable with no increase in plant safety."
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Mr. Hicks said, "This statement is erroneous and misleading. Cables in the 600
' volt class that are in good condition should withstand 20,000 volts or higher. .
i This is recognized by the industry and is included in IEEE Standards 141 and 241, both being reconenended practice manuals produced by IEEE. TVA tried to make a case in the July 13, 1987, meeting in Bethesda that degradation of cable :
insvlation after r.anufacture may occur in shipping, handling, and in the !
installation process, as well as in aging. While this is true, the degradation should not be so great that slightly more than half (10,800 volts) the above l level (20,000+ volts) could not be withstood. It is well understood that the ;
TVA process for handling and installing cabling was extremely deficient in many areas such as follows: receipt and inspection, storage, hanoling, ,
installation, testing, and quality assurance. Engineering was deficient and there was a general lack of engineering oversight for the installation, check-out, and handling and storage of cabling. One could write extensively .
about the abuses and mishandling of cabling at TVA. For brevity, one can conclude that th* ;rocess was flawed in virtually every area and any subsequent claims by TVA tv the contrary are misleading." ,
STAFF RESPONSE TO COMMENT NO. 2 The staff agrees with the test voltages proposed by TVA as stated in the Response to Comment No. 1.
4 MR. HICKS' "COMMENT NO. 3" TVA stated in the last paragraph of the letter, "In addition to the program j
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- described herein, a cable test program will be established that will be l
consistent with Inspection cnd Enforcement (IE) Notice 86-49. The program will ,
- also address low-voltage cables. The purpose will be to demonstrate margins t above the system design basis. This program will be described to NRC within
- six months after restart of SON Unit 2 and will be implemented by the end of the SQN Unit 2 cycle 4 refueling outage."
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Mr. Hicks said, "!E Notice 86-49 does not state much and does not define specific requirements, its intended compliance by TVA means little to the i
j j resolution of the cable problems, even though TVA has rade a big deal here and ,
i in the Juij 13 meeting that they will comply with this notice."
Mr. Hicks said. "There is a r-jor problem included in TVA's assumptiens for j getting NRC's approval of a , omise to develop a test program in the future.
The NRC should not be approving a program that is not yet developed by TVA.
4 Restart should not be allowed on such a basis " ]
j STAFF RESPONSE TO COMMENT NO. 3 i
TVA has performed the environmental qualification (E0) testing for silicon j rubber insulated cables,gt Wyle Laboratories ano established their margin of
- safety. This test progrant estabilshed the qualificatien life of these cables -
I for 10 years. TVA intends to perform additional E0 testing to establish the 40 l 4 year qualified life. The other cables did not experience any failures during l in-plant Hi-Pot testing. Hence, NRC approval is not based on any future test i
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l program, but is based on the testing performed by TVA to date. The periodic testing program as required by EQ and IE-IN 86-49 is not a restart issue, but could be developed by TVA as a post-restart for Sequoyah Unit 2.
MR. HICKS' "COMMENT N0. 4" Mr. Hicks sa- "TVA's statements in Item 1 of Enclosure 1 to the letter are misleading , e do not show conservatism. One cannot make a case for conservatism on an isolated item when the overall process was flawed as discussed in item 2 above '
STAFF RESPONSE TO COMMENT N0. 4 The staff's evaluation is not based on the TVA's claim of conservatism in the conduit installation. It is based on the deficiencies and problems in the cable installation practices.
MR. HICKS' "COMMENT NO. 5" TVA stated in enclosure 1, item 2, "Recent interviews of electricians who had actually performed the cable installation at Sequoyah, conducted by the NRC/ Consultants, indicated a thorough understanding of the cable installation process and the relevant concerns. These interviews substantiated conformance to proper construction practices used throughout the industry and utilization of the engineering approved installation procedures and specification and confirmed the presence of a Quality Control Inspector on all Class 1E cable pulls. In addition, the close working relationship between construction and engineering was outlined including the evaluation made before each Class lE pull to determine the best method of installation, which included determining the direction of the pull and the need for manual assistance at pull points to o reduce tensions. The testimony in these interviews was contrary to Watts Bar Nuclear Plant employee concerns in this area."
Mr. Hicks said. "These statements raise more questions. It is recent. ended that l the NRC obtain the documentation on these interviews and investigate the degree 1 of accuracy therein. Corsidering the overwhelming problems resulting from poor l practices discussed in Item 2 above, one can only conclude that the above I statements are misleading. People can have a thorough understandina during or after the fact of performing tasks, but still do sloppy and unacceptable work.
The measure of acceptability is the end product, and in this case, it is ;
unacceptable." l STAFF RESPONSE TO COMMENT N0. 5 The staff's evaluation is based on the premise that cable installation practices were deficient and the test program was developed by TVA to demonstrate the acceptability of cables. In addition, the staff ccnducted walkdowns and interviewed the licensee's craf t personnel and does not see any need to obtain TVA's documentation and investigate the issue further.
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MR. HICKS' "COMMENT N0. 6" Mr. Hicks said, "In Item 3 of the Enclosure to the letter, TVA begins to state their proposed position to sue a test voltage based on "specific minimum environmentally qualified insulation thickness for the voltage rating and in',ulation type and manufacturer." This position is weak and it does nothing to support TVA's seeking to establish an adequate margin. In fact, when one uses the minimum of anything, there is no existence of margin. This position does r.ot provide confidence that adequate margins will exist and it is not one that should be the foundation for setting an industry precedent. Further, the NRC staff assumes, from TVA's claims, that "minimum environmentally qualified voltage" is acceptable because it was the basis for Sequoyah's Operating 1.icense. I disagree, and I further challenge the NRC and TVA to prove this."
STAFF RESPONSE TO COMMENT N0. 6 The phrase, "Minimum environmentally qualified insulation thickness" means the thickness of the cable previously qualified. Sequoyah used cable insulation of greater thickness to provide additional mechanical strength and dielectric strength. Since the objective of the test program was to determine gross damage to the cable, the staff believes that testing at the voltage level corresponding to the minimum EQ insulation thickness was reasonable and has demonstrated that the insulation has not been damaged beyond a certain level.
TVA's EQ program has been reviewed by the staff and staff's evaluation is contained in NUREG-1232, Volume 2, Part 1, Section 3.2.
MR. HICKS' "COMMENT N0. 7" TVA stated in enclosure 1, item 3, "As such, use of the factory test voltage at this stage in the life of SQN cables may damage cables that are otherwise
- acceptable and inhibit a root cause determination of any test failures."
Mr. Hicks said, "This position has no basis. It entirely misses the reason for i I
testing. Known damage exists at TVA and has been verified by testing, and the very reason for testing is to find the extent of problems and replace the i I
defective cabling, thus obtaining a high confidence level for the quality of installed cabling and its ability to permit the plant to operate and shutdown safely. Any cabling that cannot meet the tests should not be left in the plant, but should be replaced."
STAFF RESPONSE TO COMMENT NO. 7 See response to comment no. 1.
l MR. HICKS' "COMMENT N0. 8",
Mr. Hicks said, "In Enc)gsure 1 of the letter and during the meeting specified in Reference 2, TVA and li's consultants quoted a number of IEEE standards.
Although a senior member of IEEE and several of its societies, I do not believe
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l that all of these standards are sufficient by themselves; for example, they I inadequately address 600 volt cabling. Referencing these standards and stating I an intent in meeting them means little and does not solve the problems at Sequoyah. The NRC should carefully review the IEEE and ICEA standards for cabling and should not the voltages in ICEA S-68-516, Revision 7, Table 3-1 j
(IPCEA S-68-516, Enclosed). I STAFF RESPONSE TO COMMENT N0. 8 The NRC staff reviewed many available standards, including TVA's letter of July 31, 1987, and determined that these standards apply to the design and installation of electrical cables. There is no single standard with complete guidance for ascertaining cable damage during installation. Also, in gdnoral, ,
l there 13 no guidance provided for the maintenance test voltage for the low voltage cables. Most of these standards apply to medium and high voltage cables. Therefore, the staff has agreed with the Hi-Pot testing based on 240V DC/ mil on the minimum EQ cable thicknesses as indicated in the staff response to comment no. I above.
MR. HICKS' "COMMENT N0. 9" Mr. Hicks said, "In Enclosure 2 of the letter, TVA refers to the use of PVC cable insulation. Why has the NRC not required TVA to replace the PVC at SQN, especially in view of the disastrous results from the Browns Ferry fire and all of the subsequent PVC restrictions? How can the NRC continue to allow plants 1 to contain PVC without having replacement programs and schedules in place to replace all PVC eventually?"
i STAFF RESPONSE TO COMMENT NO. 9
- As long as the plant meets Appendix R requirements and the functional require-ments of the cable are met, the staff does not require removal of the PVC cables.
MR. HICKS' "COMMENT N0. 10" i
Mr. Hicks said, "In Enclosure 2 of the letter, TVA explains its cable l selection / sampling criteria. More time has been spent on this than would have l oeen taken to test all of the cabling that is subject to damage."
STAFF RESPONSE TO COMMENT NO. 10 Since the cable selection criteria is based on worst case conduits, the sampling process is not random. The selection criteria as5 2 red that the worst case conduits were selected. Based on this the TVA's cable selection / sampling technique was acceptable to'the staff.
MR. HICKS' "COMMENT N0. II"'
Mr. Hicks said, "In Enclosure 2 of the letter and in the neeting specified in Reference 2, TVA tries to make a case for not testing all cables in water. l a
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Thls is contrary to commitments described to me by Mr. Raughley and Dr. Fox in a meeting in Knoxville on June 23, 1987. TVA now states that they will wet the cables on a case-by-case basis, but "It is not intended or expected that the cables will remain submersed throughout the test." To wet cables without keeping them immersed nakes no sense and will have no intended immersion effect. Either TVA tests the cables wet (immersed) or dry. There is no middle ground that could be remotely justified on this issue. Yes, it was a ridiculcus suggestion to wet test cables in all areas, but this latter proposal is even more ridiculour. The NRC should require wet immersion testing to the One degree necessary to resolve the concerns and /lsallow the TVA approach.
solution would be to remove section(s) of cabling and conduit (all intact after having been cut on both ends). Then take it outside the plant, seal one end, fill with water, and high-pot test it. Compare this with the results of dry testing."
STAFF RESPONSE TO COMMENT NO. 11 Although all the conduits could not be wetted, enough cables were wet tested to provide a reasonable assurance that there is no gross damage to the cable because of the cable installation practices at Sequoyah.
MR. HICKS' "COMMENT NO. 12" TVA states in enclosure 2, page 3, item 2, bottom, "If the cables fail the high-voltage test, the NRC will be notified promptly."
Mr. Hicks said, "The NRC should witness all tests to assure that testing is done in accord with TVA's commitment."
STAFF RESPONSE TO COMMENT NO. 12 .
The staff witnessed high voltage tests at Sequoyah. The staff was also briefed regularly by TVA on the results of each test. The staff considers this sufficient to verify TVA's compliance with the test procedures.
MR. HICKS' "COMMENT NO. 13" l Mr. Hicks said, "In Enclosure 2 of the letter, TVA provides cable acceptance criteria and what TVA will do if they have failures. The NRC must reject this plan. If failures cccur, no options should be given. All items must be tested pPior to restart and all failed items must be replaced."
Mr. Hicks said. "TVA's sampling is unacceptable and must be disallowed by the i NRC. The referenced sampling basis, hypergeometric likelihood density function !
f method, as well as any number of other statistical sampling bases, is not applicable to the subject et hand. Sampling theory, including the referenced I one, assumes that a controlled activity is occurring such as manufacturing of l like items on an assembly'line. Cable installation by different crews, in different configurations of conduit arrangements and sizes, with different l mixes and sizes of cables, and with different plant environments does not allow
classification in the same category as an assembly line type of operation. For this reason, small samples cannot be used to make conclusions about large populations of cabling."
STAFF RESPONSE TO COMMENT NO. 13 The staff's response for sampling is found in the response ts comment no. 10.
Concerning acceptance criteria, the staff will review the specific corrective action based on the root cause of the failure. This was applied to the silicon rubber insulated cables. The other cables did not have any failures.
MR HICKS' "COMMENT NO. 14" Mr. Hicks said, "In Enclosure 3 of the letter, TVA references construction specification G-38, which has been deficient from the beginning. Further, too much detail is spent on selection of conduits rather than in testing all of them. Also, TVA states that cable selection criteria will be documented in a calculation. When will it be done? It would not have to ba done if TVA would eliminate the sampling philosophy."
STAFF RESPONSE TO COMMENT NO. 14 Construction Specification G-38, Revision 8, dated March 17, 1986 was reviewed by the staff and found acceptable. This is documented in the staff's evaluation of Employee Concern Element C0-10900. TVA has also documented the ,
selection of conduits by their letter of November 20, 1987, "Cable Test Program 1 Procedures, Data and Results." The staff's response to the concerns about '
sampling are found in the staff's response to comment no. 10.
MR. HICKS' "COMMENT N0. 15" -
Mr. Hicks said, "TVA has stated that IEEE 383-1974 was not the code of record l with the implication that it did not have to follow it then or now. This is l ridiculous for a plant that had such a long construction time with delay after 1 delay, ope.*ating for a while, now shutdown for serious problems, and not wanting to agree that IEEE 383-1974 is required to solve problems. Who is kidding whom? It would be irresponsible for the NRC to allow TVA to proceed on less than IEEE 383-1974." l STAFF RESrCSSE TO COMMENT N0. 15 It is not necessary for a licensee tu comply with more recent standards than those to which the licensee committed in the FSAR, unless required by the NRC.
No such determination has been made by the staff for IEEE 383-1974.
STAFF RESPONSE TO
S The letter from Mr. Hicks cdntained several paragraphs under the heading, "General Comments." The staff felt that they were supplements to the 15 comments discussed earlier and were addressed in the staff's response.
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