|
---|
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
_ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _
, Docket Nos. 50-327 Distribution and 50-328 . Docket: Files MSimms NRC PDR" JDonohew Local PDR EJordan DCrutchfield ACRS(10)
Ms. Lola Robinson BDLiaw GPA/PA National Advertising RPierson GPA/CA Chattanooga Publishing Company BWilson SQN Rdg. File 400 East lith Street SBlack OGC Chattanooga, Tennessee 37403 JBrady ADSP Reading
Dear Ms. Robinson:
In accordance with our telephone conversation of Monday, June 19, 1989, enclosed is the Public Notice for the Sequoyah Nuclear Power Plant, Units 1 and 2 that we would like to have published on Wednesday, June 21, 1989 in the Chattanooga News-Free Press and the Chattanooga Times. Also enclosed is the Advertising Order approving this publication. After publication, please send a copy of the tear sheet and the notice to my attention. If you have any questions, please call me at 1-301-492-0796.
Sincerely, Original signed by Suzanne Black Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Enclosures:
- 1. Public Notice
- 2. Advertising Order cc w/ enclosure:
See next page f
l i 8906270009 890619 qg PDR ADOCK 05000327 y' -
old6l$ W' n OFC :NRR:TVA/L
- R M
- TVA:
/v :TVA: g:
ADq ' :0G_...__:..__}.__png..__1,__.:...________:_________
NAME :MSine : a s :RPie /h sv% : : : :
l ..___:... ..______: ........__:___...____:__..___f.....SBlack( ____________................... ____
DATE : /89 :6/g89 :6/\%/89 6/jf/89 6/Jg/89 0FFICIAL RECORD COPY l
e Ms. Lola Robinson CC:
General Counsel Mr. Kenneth M. Jenison Tennessee Valley Authority Senior Resident Inspector 400 West Summit Hill Drive Sequoyah Nuclear Plant E11 B33 U.S. Nuclear Regulatory Commission Knoxville, Tennessee 37902 2600 Igou Ferry Road Suddy Daisy, Tennessee 37379 Mr. F. L. Moreadith Vice President, Nuclear Engineering Mr. Michael H. Nobley, Director Tennessee Valley Authority Division of Radiological Health 400 West Summit Hill Drive T.E.R.R.A. Building, 6th Floor W12 A12 150 9th Avenue North Knoxville, Tennessee 37902 Nashville, Tennessee 37219-5404 l Dr. Mark 0. Medford Dr. Henry Myers, Science Advisor
! Vice President and Nuclear Committee on Interior
! Technical Director and Insular Affairs Tennessee Valley Authority U.S. House of Representatives SN 157B Lookout Place Washington, D.C. 20515 Chattar.ooga, Tennessee 37402-2801 Tennessee Valley Authority Mr. M. J. Ray, Acting Director Rockville Office Nuclear Safety and Licensing 11921 Rockville Pike Tennessee Valley Authority Suite 402 SN 157B Lookout Place Rockville, Maryland 20852 Chattanooga, Tennessee 37a02-2801 m Mr. John L. LaPoint Site Director Sequoyah fiuclear Plant Tennessee Valley Authority P. O. Box 2000 Soddy Daisy, Tennessee 37379 fir. M. Burzynski Acting Site Licensing Man 6ger Sequoyah Nuclear Plant P. O. Box 2000 Soddy Daisy, Tennessee 37379 County Judge Hamfiton County Courthuuse Chattanooga, Tennessee 57402 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Atlanta, Georgia 30323
e
, e.
PUBLIC NOTICE NRC STAFF PROPOSES TO AMEND OPERATING LICENSE AT SEQUOYAH NUCLEAR PLANT, UNIT 1 The Nuclear Regulatory Commission staff has received an application ' dated June 16, 1989, from the Tennessee Valley Authority (TVA or the. licensee) for an exigent amendment to the operating license for. the Sequoyah Nuclear Plant, Unit I located in Hamilton County, Tennessee.
If approved, the amendment temporarily would revise Specification 3.1.3.2,
" Position Indication System-Operating," to allow the licensee to use an alternative method to determine the position of a control rod in a shutdown -
bank, where the rod has an inoperable rod position indicator (RPI), .from that specified in the specification. The change would apply only for. Unit 1 until the next outage of sufficient duiation when maintenance can be performed to repair the inoperable RPI but no later than the Unit 1 Cycle 4 refueling outage scheduled ,or April of 1990. The change would also state that the provisions of Specification 3.0.4 do not apply so that the licensee may change reactor modes during this time period with the RPI inoperable.
An RPi for a Unit 1 control rod in shutdown bank D has been declared inoperable because of voltage fluctuations in the analog RPI instrumentation '
channel. Action a.1 of Specification 3.1.3.2 requires the determination of the position of the non-indicating rod indirectly by the moveable incore detectors at least once every eight hours while.the RPI is inoperable. The use of the incore detector system to comply with Action 4.1 woul J increase the use of the incore det:ctor system from once each month to 90 f t 2s each month, significantly i
~. ..
2 increasing the wear on the associated thimble tubes. The moveable incore detectors move through thimble tubes. TVA has stated that it has determined that Sequoyah, Unit 1 must be shut down to repair the inoperable RPI.
This increased use of the incore detector system and the resulting wear on-the thimble tubes are nonconservative. The concerns for the wear on these tubes were identified in NRC Bulletin 88-09, "Thi-51e Tube Thinning In Westing-house Reactors " issued on July 26, 1988. Excessive wear of the thimble tubes-results in a degradation of the reactor coolant system pressure boundary and Cdn Create the possibility of a non-isolable ledk of reactor coolant. The thimble tubes are part of the reactor coolant ' pressure boundary.
TVA has determined that the objectives of Action a.1 of Specifica-tion 3.1.3.2 can be met with an inoperable RPI in a shutdown bank without subjecting the incore thimble tubes to unnecessary additional wear. TVA will install a strip chart recorder to track the output voltage of the stationary gripper coil on the non-indicating rod (s) and verify at least once every eight hours that the non-indicating rod (s) has not changed position. This eight-hour i
surveillance period is consistent with the current operational requirements-in Action a.1 for rod position determination. If the coil has changed state, a determination of the non-indicating rod (s) position will be made by use of the i moveable incore detectors. In addition, at least once every 31 days, a full-core flux map of the Unit I core will be performed and the position of any non-indicating rod (s) will be determined using the moveable incore detectors.
This is to determine operability of the full-length control rods as required by Surveillance Requirement 4.1.3.1.2. Those periodic surveillance will provide additional assurance that the non-indicating rod (s) is in the expected position.
__ ,,_____a _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _a
3 The Comission has determined that this change should be implemented as soon as possible. The amendment would permit the licensee to continue deter-mining the position of the control rod, in the shutdown bank with the inoper -
able RPI, without subjecting the thimble tubes to excessive wear. The proposed changes have no adverse effect on safety and would be beneficial to overall plant safety. Excessive weer of the thimble tubes results in a degradation of the reactor coolant system pressure boundary and can create the possibility of a non-isolable leak of reactor coolant. The proposed change will reduce the likelihood of the re'-ctor coolant boundary being compromised and should be permitted with minimum delay. Consequently, the NRC staff has determined that exigent circumstances exist which justify reducing the public notice period normally provided for licensing amendments and proposes to issue the amendment at the close of business on June 23, 1989.
The licensee has evaluated this proposed change with regard to the determinat?,on of wnether or not a significant hazards consideration is i involved. Operation of Sequoyah, Unit 1 in accordance with the proposed 3 1
amendment will not involve a significant increase in the probability or consequences of an occident previously evaluated. The proposed change to the Sequoyah, Unit 1 Technical Specifications is to provide an alternative method for verifying shutdown rod position in the event the associated RPI becomes inoperable. The proposed change meets the intent of the current specification in that it ensures verification of position of the shutdown rod (s) once every -
eight hours. The proposed change provides only an alternative method of l monitoring shutdown rod position and does not change the assumption or j consequences of any previously evaluated accident. Therefore, the praposed i
1 i
.. g l
change will not increase the probability or consequences of any previously -
]
evaluated accident. The proposed amendment will not create the possibility of a neW.or different End of Accident from any previously analyzed. As described j above, the proposed change provides only an alternative method of determining shutdown rod (s) position. The proposed change does not affect the reactor protection system or the full-length rod control system. Therefore, the
. proposed change does not crcate the possibility of a new or different kind of accident from any previously analyzed.
The proposed amendment will not involve a significant reduction in a margin of safety. The Bases of Specification 3.1.3.2 state that the '
operability of the control RPIs is required to determine control rod positions dnd thereby ensure Compliance with the control rod alignment and insertion limits. The proposed change does not alter the requirement to determine rod position but provides an alternative and reliable nethod for determining the position of the effe:cted rod (s). Therefore, the proposed change does not reduce the margin of safety, i
Following an initial review of this application, the requested amendment has been evaluated against the standards in 10 CFR 50.92 and the NRC staff has J
made a proposed (preliminary) determination that the requested amendment involves no significant hazards considerations. The changes do not affect the possibility or consequences of any accident previously considered, nor create the possibility of an accident of a different kind, nor decrease any. margin of sa fe ty.
If the proposed determination that the requested license amendment involves no significant hazards consideration becomes final, the staff will issue the amendments without first offering an opportunity for a public
5 hearing. An opportunity for a hearing will be published in the Federal Register at a later date and any hearing request will not delay the effective date of the amendment.
If the staff decides in its final determination that the amendment does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the Federal Register and, if a hearing is granted, it will be held before the amendment is issued.
Comments on the proposed determination of no significant hazards consideration may be telephoned to Suzanne Black, Assistant Director for Projects, by collect call to 1-301-492-0796. All comments received by close of business on June 23, 1989 will be considered in reaching a final determination, A copy of the application may be examined at the NRC's Local Public Document Room located at the Chattanooga-Hamilton County Library,1001 Broad Street, Chattanooga, Tennessee 37402 and at the Consission's Public Document Room, 1717 H Street, N.W. , Washington, D.C. 20555.
~
a 200o stansers Farm No.1843 ADVERTISING ORDER DEPA3TMENT OR ESTABLISHMENT, eUAEAU 03 OFFICE oRoER uuusEn og_gg_oggg Nuclear Regulatory Commistion DATE June 19 , 1989 The pubhsher of the publication named below is authorized to publish the enclosed advertisement according to the schedule charged to private individuals with the usual discounts, it is to be below provided the rates are not in excess of the commercial rates set solid, without paragraphing, and without any display in the heading unless otherwise expressly authorized in the specifications.
$attanoo'ga'Y E Y d"I*nat"tanooga Free Press, 400 E. lith St., Chattanooga, TN 37403 SUBJECT OF ADVERTISEMENT EDIT 1oM OF PAPER ADVERTISEMENT APPEARED
_Dminvah Nuclear Plant NUMBER OF TIMES ADVERTISEMENT APPEARED
, Ohe DATE(s) ADVERTISEMENT APPEARED l SPECIFICATIONS FOR ADVERTISEMENT (ex t a va.i 1 a).1 e 14 sue - - m. ',t.$
Two column wide and deep as necessary g33g f f e f -w- O py;0h!!JcN SYMBOL 'i'/'W M pf;03 tai!CD:
- 4 W-N 5 COPY FOR ADVERTISEMENT
/ A fi n A h
~
l SEE ATTACHED
- ., . . . . . , . , ,.~
. . . , ~m;ct h3Pps/ Branch l BUSIfjESS CONTACT: Jack Donohew 1-301-492-0704; Suzie Black, 1-301-492-0796 URGENT: Division of Contracts, 1-301-492-4597 This certifies availability of FY1988 funds as follows:
Amount:$1000,Approp. Symboll:
Certifying Official: Date:
AUTHORITY TO ADVERTISE .
l NUMBER INSTRUMENT OF ASSIGNMENT NUMBER DATE DATE slGNATURE OF AUTHORIZING OFFICIAL TITLE INSTRUCTIONS TO PUBLISHERS Extreme care should be exercised to insure that the specifica-Your bill for this advertising order should be submitted on the tions for advertising to be set other than solid be definite, clear, "Public Voucher for Advertising" form, which is pri and specific since no allowance will be made for paragraphing or reverse of this form, immediately after the las'. publ for display or leaded or prominent headings, unless specifically advertisement. If copies of the printed advertisement ordered, or for additional space required by the use of type other than that specified. Specifications for advertising other than solid able, complete the affidavit provided on the voucher. Submit the and the advertisement copy submitted to the publisher will be voucher and a copy of the printed advertisement to >.. ..
attached to the voucher. The following is a sample of solid line advertisement set Up in accordance with the usual Government requirements.
DEPARTsf ENT OF E!CHWAYS & TRAFFIC.
D.C. Bids are requested for arst sprtue 1968 ee. IMPORTANT anent concrete repair contract. includlee inel-
$Na"H.'conElt n$"o7:"i.0E0,z ,i$ycQ BB sidewalk repair and 2.000 eu rda. PCC Class Charges for advertising when a cut, matrix, stereotype or electro-
- type is furnished will be based on actual space used and no allow-repa$r's*Efr'BYdIne m *'a((8I$
as tNn t'f ance will be made for shrinkage.
M,*gtge*r D,.C.ged ,g b,i,da g e in no case shall the advertisement extend beyond the date and Nmnabar is sess, edition stated in this order.
1143-307
- _ _ _ -