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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: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] |
See also: IR 05000327/1993037
Text
0
DEC 17 993
Docket Nos. 50-327, 50-328
License Nos. DPR-77, DPR-79
Tennessee Valley Authority
ATIN: Dr. Mark 0. Medfc d
Vice President. :hnical
Support
3B Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
Gentlemen:
SUBJECT: NOTICE OF VIOLATION
(NRC INSPECTION REPORT NOS. 50-327/93-37 AND 50-328/93-37)
This refers to the inspection conducted by D. Charles Payne of this office on
November 15-19, 1993. The inspection included a review of activities
authorized for your Sequoyah Nuclear Plant. At the conclusiori of the
inspection, the findings were discussed with those members of your staff
identified in the NRC Inspection Report, Enclosure 2.
Areas examined during the inspection are identified in the repor.. Within
these areas, the inspection consisted of selective examinations of procedures
and representative records, interviews with personnel, and observation of
activities in progress. A Simulator Facility Report is included in this
report as Enclosure 3, and a list of documents reviewed during the inspection
is included as Enclosure 4.
Based on the results of this inspection, certain of your activities appeared
to be in violation of NRC requirements, as specified in the enclosed Notice of
Violation (Notice). The violations are of concern because a properly
proceduralized licensed operator requalification program and proper
documentation of program activities are necessary to ensure program viability.
The ability of training department evaluators to detect weaknesses in operator
performance and properly analyze the weaknesses was noted as a program
strength. We are concerned, however, about the type and frequency of
weaknesses demonstrated by your operators during their simulator examinations.
Weaknesses were in communications, event diagnosis, understanding of control
board indications, and Emergency Operating Procedure usage.
You are required to respond to this letter and should follow the instructions
specified in the enclosed Notice when preparing your response. In your
response, you should document the specific actions taken and any additional
actions you plan to take to prevent recurrence. After reviewing your response
to this Notice, including your proposed corrective actions and the results of
future inspections, the NRC will determine whether further NRC enforcement
action is necessary to ensure compliance with NRC regulatory requirements.
9401040321 931217
, ,-
0301.31 PoR Anoca osooo327
O PDR
t\l
..
'
' Tennessee Valley Authority 2 DEC 171993
'!
l
In accordance with 10 CFR 2.790 of the NRC's " Rules of' Practice," a copy of l
this letter and its enclosures will be placed in the NRC Public Document Room. ;
!
The responses directed by this letter and the enclosed Notice are not subject j
to the clearance procedures of the Office of Management and Budget as required i
by the Paperwork Reduction Act of 1980, Pub. L. No.96-511. :
!
Should you have any questions concerning this inspection, please contact us. [
Sincerely,
ORIGINALSIGNED BY T. A.PEEBLES !
I
Thomas A. Peebles, Chief
Operations Branch
Division of Reactor Safety -
i
Enclosures:
1. Notice of Violation :
2. NRC Inspection Report l
3. Simulator Facility Report !
!
4. Documents Reviewed
cc w/encis-
Craven Crowell, Chairman ;
Tennessee-Valley Authority i
ET 12A
400 West Summit Hill Drive ,
Knoxville, TN 37902 ]
i
D. E. Nunn, Vice President !
Tennessee Valley Authority i
3B Lookout Place -
1101 Market Street l
Chattanooga, TN 37402-2801 l
l
W. H. Kennoy, Director l
Tennessee Valley Authority :
ET 12A j
400 West Summit Hill Drive i
Knoxville, TN 37902
]
cc w/encls cont'd: (See page 3) l
l
. .
-- .
'
Tennessee Valley Authority
'
d. 3
.
DEC 171993
cc w/encls. cont'd:
Johnny H. Hayes, Director
Tennessee Valley Authority
ET 12A
400 West Sumit Hill Drive
Knoxville, TN 37902
TVA Representative
Tennessee Valley Authority
Rockville Office
11921 Rockville Pike
Suite 402
Rockville, MD 20852
General Counsel
Tennessee Valley Authority
ET 11H
400 West Sumit Hill Drive
Knoxville, TN 37902
B..S. Schofield, Manager
Nuclear Licensing and Regulatory Affairs
Tennessee Valley Authority
4G Blue Ridge
1101 Market Street
Chattanooga, TN 37402-2801
Ralph H. Shell
Site Licensing Manager
Sequoyah Nuclear Plant
P. O. Box 2000
Soddy-Daisy, TN 37379
Robert Fenech, Vice President
Sequoyah Nuclear Plant
Tennessee Valley Authority
P. O. Box 2000
Soddy-Daisy, TN 37379
R. M. Eytchison, Vice President
Nuclear Operations
Tennessee Valley Authority
38 Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
cc wiencls. cont'd: (See page 4)
,
. - . . . . .. - .-
'
b
!
t
f ' ' -Tennessea Valley Atithority 4
DEC I T 933
!
t
cc w/encls. cont'd
Michael H. Mobley, Director
Division of Radiological Health .
3rd Floor. L and C Annex !
401 Church Street !
Nashville, TN 37243-1532 '
County Judge .
.
Hamilton County Courthouse '
Chattanooga, TN 37402 .
Bil'1 Harris l
Route 1, Box 26 i
Ten Mile, TN 37880 i
Mr. M. Sheperd [
.-Training Manager -i
Sequoyah Nuclear Plant
P. O. Box 2000 i
Soddy-Daisy, TN 37379
bec w/encls:
S. D. Ebneter, RII/0RA
E. W. Herschoff, RII/ ORA
J. P. Jaudon, RII/DRS
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G. A. Hallstrom, RII/DRS
J. R. Johnson, RII/DRP
P. J. Kellogg, RII/DRP .; -
S..E. Sparks, RII/DRP -
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B. M. Bordenick, 0GC ,
D. E. LaBarge, NRR :
G. Lainas, NRR i
F. Hebdon, NRR '
Document Control Desk ,
NRC Resident Inspector *
William E. Holland )
U.S. Nuclear Regulatory Commission
2600 Igou Ferry
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Soddy-Daisy, TN 37379 ',
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Document Name: g:\la\ seq \irpt9337.dep
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