|
---|
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] |
Text
-
_
- . JAN 2 91993 Docket Nos. 50-327, 50-328 '
License Nos. DPR-77, DPR-79 EA 92 251 Tennessee Valley Authority AITN: Dr. Mark 0. Medford Vice President, Nuclear Assurance, Licensing & fuels 3B Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Gentlemen:
SUBJECT: ENTORCEMENT CONFERENCE SUMMARY (NRC INSPECTION REPORT NOS. 50 327/92-37 AND 50-328/92-37)
This letter refers to the Enforcement Conference held at our request on January 13, 1993. This meeting concerned activities authorized for your Sequoyah facility. Your presentation was beneficial in clarifying the reasons for the continuing problems in your Safeguards Information Program and giving-us an understanding of your commitments for corrective actions to preclude recurrence. A list of attendees, conference summary and a copy of your-handout are enclosed. We are continuing our review of these issues to determine the appropriate enforcement actio In accordance with Section 2.790 of the NRC's " Rule of Practice," Part 2, Title 10, Code of federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Roo
Sincerely,
'
J. Philip Stohr, Director Division of Radiation Safety and Safeguards Enclosures: List of Attendees Conference Summary Handout-cc w/encls:
J. B. Waters, Chairman Tennessee Valley Authority ET 12A-400 West Summit Hill Drive Knoxville, TN 37902-(cc w/encls cont'd - See page 2)
9302160004 930129 PDR ADOCK 05000327-O PDR ,-
lf
'
.. . . . .
- _ - _ _ - _ _ - _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ - . ___ - _ _ _ _ __ . _ _ _____ __.- . ,
,
,-
Tennessee Valley Authority
_
2 JAN 2 91993 (ccw/enclscont'd)-
- J. R. Bynum, Vice President Nuclear Operations _
Tennessee Valley Authority 3B Lookout Place 1101 Maiket Street Chattanooga, TN 37402-2801 Mark J. Burzynski, Manager Nuclear Licensing and Regulatory Affairs Tennessee Valley Authority 5B Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 J. Wilson, Site Vice President Sequoyah Nuclear Plant Tennessen Valley Authority P. O. Box 2000 Soddy-Daisy, TN 37379 Marci Cooper Site Licensing _ Manager Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, TN 37379
,
TVA Representative Rockville Office 11921 Rockville Pike Suite 402 Rockville. MD 20852 General Counsel Tennessee Valley Authority ET llH-400 West Summit Hill Drive Knoxville,'TN 37902 County Judge llamilton County _ Courthouse Chattanooga, TN 37402
~
..
~ Michael H. Mobley, Director l Division.of Radiological Health
! : 3rd Floor,:L'and C Annex 401 Church Street-Nashville,' TN 37243-1532 L:
bec: (Seepage 3)-
l L
4;1 + m w p- e .*r. -
. _ - _ _ _ _ _ _ _ _ - - _ - _ _ - _ _ _ _ _ _ _ _ _ _ -
'
, ;'. .l q
!
Tennessee Valley Authority 3 JM 2 9 M f-bcc w/encis: )
-E. Herschoff, R!l J.. Johnson,- Ril r P. J. Kellogg, Ril J. B. Brady, Ril ,
B. Bordenick. 000'
D. E. LaBarge, NRR i G. Lainas, NRR J. Lieberman, OE R. Rosano, OE F. Hebdon. NRR .
!
Document Contrcl Desk-NRC Resident Inspector .
U.S. Nuclear Regulatory Commission <
2600 Igou Ferry ,
Soddy Daisy,-TN 37379
.
.
'k
Ril:DRSS Ril:DRSS RII:DRSS -Ril:DRSS Ril:DRP
.* * * p, *
OMasnyk DMcGuire DMCollins BSMallett- -PKellogg
-//93 //93 /-/93- _t/ /93 ././9 .
' ~
RII:0R RII:ROA
GJenkins 'CEvans
-//93 /_/93 (*) SEE PREVIOUS PAGE FOR. CONCURRENCES
>
. }
. . . . . - - . . . . . --
.. . _ _ _ . . _ _ .
. _ - - - _ .. . . - - - _ - - - _ _ _ _ . - . - - - . _ - _ - - _
. . . .
. .
g
'
n'
-
Tennessee Valley Authority 3 JM 2 91993 bec w/encis:
E. Merschoff, Rll J. Johnson, Ril 'N '
P. J. Kellogg, Ril J. B. Brady, Rll B. Bordenick, OGC N'x
'
D. E. LaBarge, NRR G. Lainas, NRR of -- --
f. Hebdon, NRR - I NW#p % ~~~
Document Control Desk p,,C'osed)06 -
NRC Resident inspector U.S. Nuclear Regulatory Conunission 2600 Igou Ferry Soddy Daisy, TN 37379 l ,
.
%_
\ s
-
?
Ril:DRhs Ril:DRSS Ril:DRSS RII:
OJtrl /Rin]RSS j!u . FM OMasnyk Wr50ffre DMCollins BSMallett PKe ogg l/N93 (/tJ93 ' /ll/93 g /q/93 (g/93 KI A) RII:ROA
,
ff cf's
{J s CEvans
/ /p 2 3 //r/93 l
_ _ _ _ _ - - _ _ - - - _ _ _ _ _ _ _ - - _ - _ _ - - - _ - _ _ - - _ _ _ _ _ _ _
'
. .
'
Enclosure 1 List of Attendees LS.- Nuclear Requlatory Commission Region 11 D. Collins, Chiaf, Nuc' storial Safety and Safeguards Branch C. Evans, Regional Cot . o G. Jenkins, Director, Enforcement and Investigat. ion Coordination Staff P. Kellogg, Chief, Division of Reactor Projects, Section 4A -
,
0. Masnyk, Safeguards Specialist D. McGuire, Chief, Safeguards Fection L. Reyes, Deputy Regional Administrator J. Stohr, Director, Division of Radiation Safety and Safeguards L. Stratton, Physical Security Specialist D. Thompson, Physical Security Inspector W. Tobin, Senior Safeguards Inspector B. Uryc, Senior Enforcement Specialist B. Wilson, Chief, Division of Reactor Projects, Branch 4 Office of Enforcement R. Rosano, Senior Enforcement Specialist Tennessee Valley Authority J. Bynum, Vice President, Nuclear Operations M. Burzynski, Corporate Licensing Manager R. Fenech, Site Vice President, Sequoyah T. Flippo, Site Quality Manager C. Kelley, Corporate Security Manager M. Medford, Vi'.e President, Nuclear Assurance J. Setliffe, site Security Manager R. Thompson, Compliance Licensing Manager
._____-______ _ _ _ _ _ .. .. .
- ____ . _ _ _ _ ____ _- _ - _ - _ _ - _ _ _ _ - _ - _ _ _ _ . _ _ _
. .
Enclosure 2 Enforcement Conference Summary An Enforcement Conference was held on January 13, 1992, at the Region 11 office to discuss the recurring problems relating to the protection of Safeguards Information at the Sequoyah Nuclear Plant, and the licensee's failure to log all of these events in the Safeguards Quarterly lo The Deputy Regional Administrator expressed concern with the continuing -
problems in the Safeguards Information Program and with the licensee's failure to recognize the problems and their significance. The Director of the Enforcement and Investigation Coordination Staff explained the enforcement process and those portions of the policy pertinent to this conference. The Director for the Civision of Radiation Safety and Safeguards recapped the NRC's understanding of the apparent violations and the regulatory requirement Licensee officials provided a briefing outlining the causes for the apparent violations and the implemented and proposed corrective measure This briefing is contained in Enclosure 3 to this report.
. .. __ _ _ _ _ _ _ - - _ - _ _ - - _ _ _ _ _ _ _ _ _ _ -
ENCLOSURE 3 TVA/NRC ENFORCEMENT CONFERENCE -
SGI CONTROL EVENTS IR 327, 328/92-37 JANUARY 13,1993
-
.
, ..
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT ENFORCEl\ENT CONFERENCE PRESENTATION = .
'
SGI CONTROL EVENTS:-
JANUARY 13,.1993 f
W
._
_ - _ _ - - - -
.
.
I
AGENDA INTRODUCTION R. FENECII (Site V.P.)
I DISCUSSION OF SAFEGUARDS EVENTS C.KELLEY (Corp. Sec. Mgr.)
- TRENDING & SELF-ASSESSMENT g
- DISCUSSION OF SPECIFIC EVENTS III. QA INVOLVENENT T. FLIPPO (QA Mgr.)
IV. REGULATORY PERSPECTIVE M. BURZYNSKI (Corp. Lic. Mgr.) CLOSING REMARKS / CONCLUSIONS R. FENECII
I
_---- _ ___
_ - _ - _ _ ..
'. .
DISCUSSION OF SAFEGUARDS EVENTS SUhBIARY OF EVENTS TIME FRAME
- 8 EVENTS IN 1991 e 10 EVENTS IN 1992 g
18 EVENTS FALL INTO 6 CATEGORIES
- 2 FAULTY STORAGE EQUIPMENT
- 1 FAILURE TO PROPERLY MARK
- 7 FAILURE TO ADEQUATELY PROTECT
- 1 FAILURE TO UPDATE SGI ACCESS LIST
_-_-___-_ - _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - -
. - _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
DISCUSSION OF SAFEGUARDS EVENTS REPORTABILITY DEVELOPMENT OF TVA REPORTING STANDARDS
- PARTICIPATION IN SOUTII EAST NUCLEAR SECURITY ASSOCIATION (SENSA)
- NRC GUIDANCE - GENERIC LETTER 91-03 IIOW REPORTABILITY STANDARDS OPERATE
- SIGNIFICANT SGI (LOST /COh1 PROMISED) = 1 IIr CALL
- SIGNIFICANT SGI (NOT LOST /NOT COMPROMISED) = LOGGED l
- NON-SIGNIFICANT SGI (LOST / COMPROMISED) = LOGGED
- NON-SIGNIFICANT SGI (NOT LOST /NOT COMPROMISED) = NON-EVENT REPORTABILITY OF EVENTS
- BASED ON ABOVE, ORIGINAL DETERMINATION - 5 EVENTS LOGGABLE
- REPORTABLE & NON-REPORTABLE EVENTS RECORDED IN INTERNAL SECURITY LOG
- TVA's REPORTABILITY DETERMINATIONS WERE DIRECTLY RELATED TO OVERALL SIGNIFICANCE
,,, .. ._
-
.
DISCUSSION OF SAFEGUARDS EVENTS REPORTABILITY (CONTINUED)
SOME TYPICAL FACTORS USED IN SIGNIFICANCE DETERMINATION
- COMPROMISE O'R LOST SGI '
- IMPORTANCE OF INFORMATION I
- COULD INFORMATION.BE DECLASSIFIED e ACCESSIBILITY BY UNAUTHORIZED PERSONS
_
..
_
DISCUSSION OF SAFEGUARDS EVENTS I
REPORTABILITY ,
(CONTINUED)
5 LOGGED EVENTS DURATION LOCATION DECLASSIFIED ACCESSIBILITY DATE DESCRIITION COhfPROa1ISE IntPORTANCE l
l N N 01/16/91 UNSECURED N N s 4 Ifrs SECURED LOCATION l CABINET 2: 24 IIrs SECURED N N STORED IN N N 04/21/91 l LOCATION UNAPPROVED l CABINET s 16 Ifrs SECURED 'N N 10/23/91 UNSECURED N Y LOCATION CABINET 2 Yrs N/A N UNK 04/10/92 LOST SGI N N N IEIDID IUIENIlu, -
N Y 7 Afos OIITSIDE PA 09/18/92 FAILURE TO CONTROL SGI
'
l L:
- _ _ - - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
P DISCUSSION OF SAFEGUARDS EVENTS TRENDING /SELF-ASSESSNENT MONTHLY REPORTS
- SELF-AUDIT REDUCED THE NUMBER OF SGI CONTAINERS
- ERCW BADGING PROCESS CHANGED e PHYSICAL SECURITY UPGRADE PROJECT INITIATED g
ROOT CAUSE ANALYSIS COMMITTEE
- CHANGED PA BADGE ISSUE PROCESS OUALITY IMPROVEMENT TEAM (OIT)
- REDUCED NUMBER OF SGI CONTAINERS
- REDUCED NUMBER OF SGI CUSTODIANS 7 l
. . . . . . _ _ _
'
'
,, ,
'
l
l> --DISCUSSION OF SAFEGUARDS EVENTS
_ _ _.
"
ROOT CAUSES
-* TVA REPORTING STANDARD RESULTED IN NON--
LOGGED EVENTS e INATTENTION TO - DETAIL RESULTED IN FAILURE-TO ADEQUATELY CONTROL SGI- _
e- 'NOT INCLUDING " EXTENT OF . CONDITION" AND/OR-:" PRIOR SIMILAR EVENTS" IN REVIEWL l OF ROUTINE INCIDENTS LED- TO LACKi OF RECOGNITION FPOTENTIAL ADVERSETREND d PRINCIPAL CONTRIBUTING FACTORS: 4
-
<
'
- --
. . . . . ._ . . . .. .~
'
~ .
s -f
'
.
..;
'
DISCUSSION OF SAFEGUARDS EVENTS
,
_
CORRECTIVE ACTIONS
-
CONTRIBUTING CAUSES
,
'
- QIT EFFORT REPORTING-STANDARD q- * FOUR EVENTS LOGGED.ON NRC 24'Hr. LOG TO' BE INCLUDE ON QUARTERLY SAFEGUARDS EVENT
-* SAFEGUARDS EVENTS . NOT.- REPORTED 1 IN -PREVIOUS QUARTERS BACK-TO 3/6/91;WERE LOGGED:INTO THE:24 Hr:
LOG AS A SINGLE ENTR :
- LETTER ISSdED TO ' SITE SECURITY SUPERVISORS REQUIRING i ,
ALL~ SGI EVENTS TO BE LOGGED ON THE 24 Hr EVENT LOG' -
-* THRESHOLD FOR REPORTING-OF ' SAFEGUARDS EVENTS. HAS ?
BEEN CHANGED AT OTHER TVA NUCLEAR SITES . ~
~ .
.
P'
9-
'
_
- _ _ _ _ __
}
DISCUSSION OF SAFEGUARDS EVENTS CORRECTIVE ACTIONS INATTENTION TO DETAIL
- ISSUED LETTER TO SQN SAFEGUARDS CUSTODIANS REQUIRING USE OF SIGNS AND ACCOUNTABILITY LOGS
- PROVIDED UPGRADED TRAINING TO CUSTODIANS ON SGI CONTROL
- VEIUFIED USE OF CONTAINER SIGNS AND ACCOUNTABILITY
- REVISED PROCEDURE REQUIRING USE OF JGNS AND ACCOUNTABILITY LOGS NARROWLY FOCUSED INCIDENT REVIEWS
- REVISED PROCEDURE TO ENSURE SFCURITY EVENT INVESTIGATIONS INCLUDE: (I) EXTENT OF CONDITION; (2) SEARCII FOR PRIOR SIMILAR EVENTS; (3) DETERMINATION OF "REAL" ROOT CAUSE; AND (4) FORMAL TRACKING OF EVENT ACTIONS
- PERFORMED TREND ANALYSIS OF OTIIER SECURITY EVENTS AND INITIATED APPROPRIATE ACTIONS, WIIGE NEEDED-
- REVISED PROCEDURE TO ENSURE AT LEAST ONEMEMBER OF SECURITT EVENT INVESTIGATION TEAM IS TRAINED IN ROOT CAUSE ANALYSIS METIIODS
- REVISED PROCEDURE TO REQUIRE INCLUSION OF SECURITY EVENTS IDENTIFIED AS ADVERSE TRENDS INTO NER PROGILGI
_
w
_- - - -. . . -- - . . -.
,
-
, ,
-
<l
- n _
DISCUSSION OF SAFEGUARDS EVENTS j u
.
' SALE OF SGI CONTAINER' i
r OVERVIEW OF EVENT ;
- UNAUTHOKIZED CONTAINER - ISOLATED OCCURRENCEr
+ * OLD EVENT - SIGNIFICANT. PROGRAM ENHANCEMENTS: HAVE OCCURRED SINCE THE *- IN DEITH INVESTIGATION SHOWED LIMITED.PO ENTIAL"FOR COMPROMISE -
REPORTABILITY '
>
- NO COMPROMISE, ALTHOUGH ' INFORMATION CONSIDEREDj SIGNTICANT
- - INCIDENT DISCUSSED WITH NRC STAFF ' l ROOT CAUSE
- UNAUTHORIZED.CONTAINERLNOT ON APPROVED SAFEGUARDSL CONTAINER LIST t
CORRECTIVE ACTIONS
-* NOW ONLY UECURITY CAN ESTABLISH CONTAINERS =-
- EXTRA S&G LOCKS NOW UNDER SECURITY CONTRO * RETRAINED CORP. ENG. SGI HANDLERS
~e- l INTERVIEWED - CORP._ -ENG.. ' CUSTODIANS? LTO. eASSURE 5NOl ADDITIONAL _ UNAUTHORIZED CONTAINERS
.
.
- - - PERSONNEL SENSITIZED THAT LOCKED CONTAINERS ARE NOT TO; ;
BE MOVED UNTII1 SECURITY-INVENTORIES CONTEN'I'S : }
') - .
'
-
. + s, , s+ , . - , , - , - - > . - - ,, --
.. . - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ - _ _ _ _ _ _ _
.
DISCUSSION OF SAFEGUARDS EVENTS IMPROPER MARKING OF CHANGE NOTICE OVERVIEW OF EVENT
- INVOLVED PARTIAL WIRING DIAGRAh!
- SIIORT DURATION REPORTABILITY
- ALTIIOUGII APPROPRIATELY h!ARKED AS SAFEGUARDS, BY ITSELF, NOT AN IMPORTANT DOCUh1 FAT
"
ROOT CAUSE
- ISOLATED - PERSONNEL ERROR C_ORRECTIVE ACTIONS
12
. . . . . . . _ _ _ _ . _ . _ . _ _ _
_j
- - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _
.
.. ~
DISCUSbiun OF SAFEGUARDS EVENTS INCIDENT CONCERNING UPDATE OF SGI ACCESS LIST OVERVIEW OF EVENT
- INVOLVED INPO CONTRACTOR e ISOLATED OCCUlUENCE REPORTABILITY t,
- HAD NO ACCESS TO SGI ROOT CAUSE e FAILURE TO PERIODICALLY UPDATE ACCESS LIST CORRECTIVE ACTION
- ADDITIONAL MANAGEMENT R2 VIEW REQUIRED
_ .. . _ _ - _ - _ _ - _ - _ - - _ _ _ _ _ - - _ - - _ - - _ _ - _ - _ - _ _ _ _ - _ _ _ _ _ _ ._ _ _ _ . .a
. y s- ',
.
~
a
'
'_ '
QA OVERSIGHT EFFORTS DURING-1991-921
- - - TWO ANNUAL NUCLEAR POWER WIDE PERFORMANCE; BASED AUDITS
- AUDITS ADDRESSED SGI CONTROLS'
- SECURITY EVENT LOGS WERE EVALUATED
-
NO ADVERSE TRENDS IDENTIFIED
'
e -PERFORMANCE BASED ASSESSMENTS ,
'
-
'(5/91) : INITIATED FIR ADDRESSING INADEQUATE : TREND ANALYSIS FOR SGERs ,
-
-
(4/92) QA IDENTIFIED SGI CONTROL EVENT
_.
. -
(10/92) QA IDENTIFIw SGI CONTROL EVENT
'I
'
- QUARTERLY TREND REPORTSL <
.
- NO SIGNIFICANT ADVERSE TRENDS WERE IDENTIFIm
.
. -CONCLUSION: SIGNIFICANT - ADVERSEL TRENDSL ?WERE H NOT" APPARENT BASED ON QA's OVERSIGIIT EFFORTS
- y
'
FUTURE - ACTIONS: L-(1) LOOK A SECURITY LEVENTSHOVER L A:
~
n BROADER TIME FRAME &-(2) STRENGTHEN: TREND ANALYSIS TOL - ^
- EVALUATE NON-REPORTABLE SAFEGUARDS EVENTS e
,
j,_ , 1 ,
'
L n
. .. -
., - . _ .. . _
- - . - . - . --- - --
' ' ' ' -
,
o j
REGULATORY PERSPECTIVE
- BASED ON REVISED -ENFORCEMENT- POLICY (2/92)
INCREASES THRESHOLD FOR SIGNIFICANT SECURITY VIOLATIONS ;
- RELEVANT ENFORCEMENT PRECEDENT SUPPORTS-NON-ESCALATED ACTION
- INDIVIDUALLY,- EVENTS OF MINIMAL SAFEGUARDS :
SIGNIFICANCE
- AS A WHOLE. EVENTS DO NOT REPRESENT i A '
BREAKDOWN IN- OVERALL- SECURITY -PROGRAM ~
EFFECTIVENESS
.
- PROMPT & EFFECTIVE CORRECTIVE TACTIONSlFOR ^
NRC's CURRENT CONCERNS IRVE BEEN-TAKE t t
.
4
.
, ; *
REGULATORY PERSPECTIVE (CONTINUED)
- SALP 1 FOR 'ITVO PERIODS - SHOWS SECURITY
-
PROGRAM REMAINS EFFECTIVE e- NRC REVIEW OF SECURITY PROGRAM EFFORTS--
AUGUST 1992-INSPECTION REPORT!No, 92-23'
"The licensee has instituted a Root Cause Analysis committee to investigate self identified failures of personnel and equipment . . . . Safeguards Event less-(10 CFR 73.71) are
.
reviewed and analyzed as part of this self audit /self-corrected effort."
OCTOBER 1992 SALP REPORT No.- 92-26
"Self assessments were superior . . . . Additional compliance audits from Corporatd Nuclear '
Security.and site security organintions provided extensive self assessment. -- Ront Caune-analysis' and human performance evaluations assure.' corrective actions were effective.-
Trending of Safeguards Event Logs by security management resulted in pro active measures 7
- GOOD FAITH EFFORT ON REPORTING CRITERIA- MADE THROUGH SENSA-PARTICIPATION ~ y OVERALL - CONC'LUSION: ESCALATED :ENFORCEMENTjISL NOT WARRANTED
_ a
'
I; I --
g i
l)
,
i a ,- .,
. ..
i FINAL REMARKS
.,
.
L h
.
.
&
_ %
.
, . ,
,4
-
l
.
.
-
- - .
'
l' (; t
,r u
'
l,
,.
r
-
u f-
f. . i L 17. - .-!.
, ; --
. . ;=
'
' l1 ... .
, JAdf -J '- .
-ja1 \. <
L .d ij: '
i h ) ,* . ..
+; . - m..-- ,, .
,
-
. _ . _ . . , ,