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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 05000327/1997013
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December 8, 1997
EA 97 409
Tennessee Valley Authority
ATTN: Mr. O. J. Zeringue,
Chief Nuclear Officer and
Executive Vice President
6A Lookout Place
1101 Harket Street
Chattanooga, Tennessee 37402 2801
SUBJECT: NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY -
$55,000 (NRC SPECIAL INSPECTION REPORT NOS. 50 327/97 13 AND
50 328/97 13)
Dear Mr. Zeringde:
This refers to the special inspection conducted on July 25 through
September 4,1997, at the Sequoyah facility. The purpose of the inspection
was to review the misalignment of spare vital battery No. V to vital battery
board No. IV on July 24, 1997. The results of the inspection were sent to you
by letter dated September 11, 1997. An open, predecisional enforcement
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conference was conducted in the Region II office on November 19, 1997, with
you and members of your staff, to discuss the violations, the root causes, and
your corrective actions to preclude recurrence. A list of conference
attendees and copies of the Nuclear Regulatory Commission's (NRC) and
Tennessee Valley Authority's (TVA) presentation materials are enclosed.
Based on the information developed during the ins)ection and the information
that was provided during the conference, the NRC 1as determined that
violations of NRC requirements occurred. The violations are cited in the
> enclosed Notice of Violation and Proposed Imposition of Civil Penalty
(Notice), and the circumstances surrounding them are described in detail in
the subject inspection report.
On July 24, 1997, a Senior Reactor Operator (SRO) failed to realign rpare
vital battery No. V to vital battery board No. IV properly, after hanging a
clearance on 125 volt direct current (DC) vital battery No. IV. As a result, j
vital battery board No, IV was inoperable for approximately 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Based /
on the additional information that was provided during the conference, the NRC
concluded that three violations of regulatory requirements occurred. The
violations include: (1) the failure to meet Technical Specification (TS)
3.8.2.3 requirements to maintain four DC vital battery channels energized and
operable: (2) the failure to follow procedures associated with realigning the
spare vital battery No. V to a vital battery board: end, (3) the failure to
follow administrative procedures to ensure that the position of 125 volt DC
distribution system breakers were subject to independent verification. These
violations and a number of other concerns described below indicate serious
weaknesses in the performance of the operations staff. In this case, the 'f,
operations staff demonstrated a lack of inquisitiveness and a lack of strict 'l([U
adherence to procedures in performing the realignment of the vital Lattery. /
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9712300237 971200
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During this event, the SR0 went to the wrong distribution panel to close a l
breaker and found a breaker with similar labels already closed, Although the
SR0 questioned the unexpected breaker status, he failed to adequately
investigate the discrepancy, did not notify the control room of the >otential
configuration control issue, and did not note the failure to close t1e breaker
as a deviation from the procedure. Several steps later in the procedure, he
opened the same breaker yet failed to recognize the incongruity. At the
conference, you stated that your procedures and expectations in this situation
allow the cognizant supervisor, i.e., the SRO, to resolve the discrepancy:
yet, the SRO was closely involved in performing the steps of the
which compromised his ability to oversee the work independently, procedure
Problems with auxiliary unit operator (AVO) rounds practices were also noted.
Tests of the batteries indicated that it is likely that the battery voltage
was below required surveillance limits at the time AVO rounds were performed;
however, the AVO failed to identify reduced voltage at the board. Control
room operators initially performing the battery realignment, and subsequent
oncoming crews, did not identify the lack of an expected main control room
alarm, and the procedure did not highlight that an alarm was expected.
Lastly, an SRO entered an incorrect Technical Specification action statement
during the initial vital board realignment.
The root causes of the misalignment event, i.e., the failure to evaluate the
unexpected as found condition and/or weaknesses associated with component
labeling, were similar to previous events. NRC Inspection Report 50 327,-
328/97 03 documented an event in which an operator found a valve in an
unexpected position and did net notify the control room, resulting in the
isolation of the spent fuel pool cooling pump for about two hours while the
pump was running. Enforcement Action 97 232, issued on July 10, 1997,
documented operator errors in investigating discrepant indications of reactor
coolant system (RrS) level resulting in an RCS drain down event. Licensee
Event Report (LER) 95 08 documented a reactor trip which occurred when an
operator opened a wrong breaker on the wrong vital 120 VAC board.
The NRC recognizes that the actual safety and risk significance of the
inoperable vital battery board was mitigated by the fact that a spare battery
charger was aligned to the board and the charger would have provided power to
the board in all scenarios except for a loss of offsite power. In addition,
the NRC commends the training instructor who recognized that the vital battery
board su) ply breaker was not in the correct >osition and took prompt action to
notify tie Operations staff. Nonetheless, t1ese violations are of significant
regulatory concern to the NRC due to: (1) problems in the performance of the
operating staff: (2) the fact that multiple opportunities existed to prevent
and detect the inoperability of the vital battery board; and, (3) previous
events involving similar operator errors and problems attributable to
component labeling have occurred and corrective action did not preclude
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repetition of the problems. Therefore, the violations have been categorized
in the aggregate in accordance with the * General Statement of Policy and
Procedures for NRC Enforcement Actions" (Enforcement Policy). NUREG 1600, as a
Severity Level !!! problem.
In accordance with the Enforcement Policy, a base civil penalty in the amount
of $55.000 is considered for a Severity Level !!! problem. Because your
facility h
two years,ps been the sub4ect of escalated enforcement actions within the last
theNRCconsideredwhethercreditwaswarrantedforidentification
and Cg rective Action in accordance with the civil penalty assessment process
descri >ed in Section VI.B.2 of the Enforcement Policy. NRC determined that
credit was not warranted ' * identification because prior opportunities to
identify the violations existed. Your corrective actions included:
(1) revising the operating procedure to require independent verification of
breaker position: (2) hanging caution tags on the five No. 107 breakers to
ensure proper identification: (3) plans to relabel all 125, and 250 volt DC
and 120 volt AC boards: (4) developing job performance measures for work on
the 125 volt DC batteries: (5) revising the battery procedure to identify the
No. V battery in service alarm, including the appropriate TS action statement
in the battery procedure: (6) reviewing other operations and me.intenanco
procedures to ensure proper independent verifications have been identified:
and (7) taking appropriate personnel actions. Based on the above, the NRC
determined that credit was warranted for the factor of Corrective Action.
Therefore, to emphasize the importance of attention to detail and appropriate
implementation of TS requirements, and in recognition of your previous
escalated enforcement actions. I have been authorized, after consultation with
the Office of Enforcement, to issue the enclosed Notice of Violation and
Proposed Imposition of Civil Penalty (Notice) in the base amount of $55,000
for the Severity Level 111 problem.
The apparent violations identified in NRC Inspection Report No. 50 327,
328/97 13 included a failure to stop the e?lution when a procedural step
could not be performed and failure to prom ly identify an adverse condition
(out of tolerance battery voltage). At ths predecisional enforcement
conference, you indicated that, although your expectations for operator
performance were not met in these areus, you concluded that procedural
requirements had been met. Because these circumstances were factored into our
assessment of prior opportunities to identify the breaker misalignment, these
apparent violations are withdrawn. In additich, at the conference, you
provided information indicating that AVO rounds to assess battery room
temperature and battery voltage on vital battery No. V were appropriate. This
apparent violation is also withdrawn.
8
A severity Level til problem was issued on July 10.1997. (EA 97 232), for violat; .s
associated with a reactor coolant syttem (RCs) inadvertent drain down. Two severity Level 111
protlems and proposed civil penaltie- af $50,000 each were issued on December 24, 1996. (EA 96-
414L for inadequate corrective actions related to maintenance of reactor trip breakers and other
equipment. A severity Level !!! violation and proposed civil penalty of $50,000 was issued on
November 19.1996. (EA 9s 269), related to fire protection program deficiencies. A severity
level 11 violation and roposed civil penalty of $80,000 were issued on February 20, 1996. (EA
2 . related to emp oyee discrimination in Department of Labor Case Nos. 92 ERA 19 and 92-
. _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ .. _
..
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I
You are required to respond to this letter and should follow the instructions !
specified in the enclosed Notice when preparing your response. In your i
response, you should document the specific actions taken and any additional ;
actions you plan to prevent recurrence of the violations. After reviewing I
, your response to this Notice. including your proposed corrective actions and i
'
the results of future inspections. the NRC will determine whether further NRC :
enforcement action is necessary to ensure compliance with NRC regulatory ;
'
requirements.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice." a copy of
this letter and its enclosures will be placed in the NRC Public Document Room. j
'
-
Sincerely.
Original signed by
Bruce S. Mallett
Luis A. Reyes
Regional Administrator
'
Docket Nos. -50 327. 50 328
License Nos. DPR 77. DPR 79
Enclosures: 1. ~ Notice of Violation and Proposed
4
Im>osition of Civil Penalty
2. NRC 'resentation Materials
3. TVA Presentation Materials
4. List of Attendees
cc w/encls: ,
Senior Vice President
Nuclear Operations ,
Tennessee Valley Authority t
6A Lookout Place ,
1101 Market Street i
- Chattanooga TN 37402 2801 -
Jack A. Bailey. Vice President
Engineering & Technical Services
Tennessee Valley Authority -
6A Lookout Place
- 1101 Market Street >
Chattanooga. TN 37402 2801 !
cc w/encls cont'd: See page 5 l
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TVA 5
cc w/encls cont'd:
HasoudBajestani
Site Vice President
Sequoyah Nuclear Plant
Tennessee Valley Authority
P, O. Box 2000
Soddy Daisy, TN 37379
General Counsel
Tenressee Valley Authority
'
ET 10H
400 West Sumit Hill Drive
Knoxville, TN 37902
Raul R, Baron, Ge'1eral Hanager
Nuclear Assurance
Tennessee Valley Authority
4J Blue Ridge
1101 Harket Street
Chattanooga,TN 37402 2801
Hark J. Burzynski, Manager
Nuclear Licensing
Tennessee Valley Authority
4J Blue Ridge
1101 Market Street
Chattanooga, TN 37402 2801
Pedro Salas, Manager .
Licensing and Industry Affairs
Sequoyan Nuclear Plant
P. O. Box 2000
Soddy Daisy, TN 37379
J. T. Herron, Flant Manager
Sequoyah Nuclear Plant
Tennessee Valley Authority
P, O. Box 2000
Soddy Daisy, TN 37379
Director
Division of Radiological Health
3rd Floor. L and C Annex
401 Church Street
Nashville, TN 37243 1532
County Executive
Hamilton County Courthouse
Chattanooga, TN 37402
_ _ _ _ _ _ - . _ _ _ - _ _ _ _ - _ _ _ _ _ - _ _ _ - _ _ - _ _ _ _ _ _ _ __ _ _ _ _ - _ _ _ - _ _ _ _ _ -- _ _ . __ _ ___ . _ _ _ .
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IVA 6
Distribution w/eric1-1:
M LIC
LJCallan, EDO
HThompson, DEDR i'
Alhadani, DEDE
LTrocine OE00
LCh;adler 0GC '
JGoldberg, OGC
RZimmerman, NRR
EJulian, SECY r
BXeeling,CA
Enforcement Coordinators
RI, RIII, RIV
JLieberman, OE ,
OE:EA File (BSummers) (2 letterhead)
-DNelson, OE -
EHayden, OPA
GCaputo, 01 1
THartin, AE00 ,
HBell, DIG
FHebdon, NRR '
RHernan, NRR
CEvans, RII
ABoland, RII
JJohnson, RI!
JJaudon, RII
HLesser, RII (IFS Actioti Required)
SS) arks, RII
HW1itener, RI!
JHoorman, RII
KClark, RII-
RTrojanowski,RI!
LWatson, RI!
NRC Resident Inspector, Operations
V. S. Nuclear Regulatory Commission
1260 Nuclear Plant Road
Spring City. TN 37381
NRC Resident inspector
Seq,.oyah Nuclear Plant
'U.-S, Nuclear Regulatory Commission- ,
2600 Igou Ferry Road
Soddy Daisy, TN 37379
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BKeeling,CA ;
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R1, RIII, RIV
JLieberman, OE -
OE:EA File (BSummers) (2 letterhead)
DNelson, OE ,
EHayden, OPA
GCaputo 01 +
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FHebdon, NRR i'
RHernan, NRR -
CCvans, RII ~
ABoland, RII
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JJiudon, RII
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SS) arks, RII
HW11tener, RII
JHoorman, RI!
KClark, RII
RTrojanowski,RII
LWatson, RII ;
NRC Resident Inspector, Operations !
U. S, Nuclear Regulatory Commission
1260 Nuclear Plant Road r
Spring City, TN 37381
NRC Resident Inspector
Sequoyah Nuclear Plant
U. S Nuclear Regulatory Commission
2600 Igou Ferry Road' ,
Soddy Daisy, TN 37379
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JGoldberg, OGC
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Enforconent Coordinators
RI. RIII, RIV -!
-JLieberman, OE -
OE:EA File (BSumers) (2 letterhead)
DNelson, DE l
EHayden, OPA
GCaputo 01
THartin, AEOD '
HBell. 0!G .
fHebdon, NRR
RHernan, NRR
CCyans, RII
ABoland, RII
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JJaudon, RII
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SS) arks, RII
HW11tener, RII
JHo,rman, RII
KClark, RII L
RTrojanowski, RII
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NRC Resident Inspector, Operatiors
'l.- S.: Nuclear Regulatory Comission
.. Nuclear Plant Road
Spring City, TN 37381
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NRC Resident Inspector
Sequoyah Nuclear Plant <
4 U. S. Nuclear Regulatory Comission
2600.Icou Ferry Road . .
Soddy Daisy,-TN. 37379
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