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| {{Adams | | {{Adams |
| | number = ML20213G976 | | | number = ML20236B007 |
| | issue date = 05/04/1987 | | | issue date = 07/22/1987 |
| | title = Requests Evaluation of Util 861024 & 870406 Denials of Violation 86-42-01 & Unresolved Item 86-42-02 from Insp Repts 50-327/86-42 & 50-328/86-42 Re Environ Qualification of Asco Solenoid Valves | | | title = Advises That Based on Listed Addl Discussions & info,870406 Response Denying Violation Noted in Insp Repts 50-327/86-42 & 50-328/86-42 Valid.Example 2 of Subj Violation Withdrawn. Util Statement Re Solenoid Qualification Data Clarified |
| | author name = Zech G | | | author name = Zech G |
| | author affiliation = NRC OFFICE OF SPECIAL PROJECTS | | | author affiliation = NRC OFFICE OF SPECIAL PROJECTS |
| | addressee name = Liaw B | | | addressee name = White S |
| | addressee affiliation = NRC OFFICE OF SPECIAL PROJECTS | | | addressee affiliation = TENNESSEE VALLEY AUTHORITY |
| | docket = 05000327, 05000328 | | | docket = 05000327, 05000328 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = TAC-R00110, TAC-R00111, TAC-R110, TAC-R111, NUDOCS 8705190073 | | | document report number = NUDOCS 8707280301 |
| | document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 2 | | | page count = 2 |
| }} | | }} |
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| ,. N MAY 0 41987 MEMORANDUM FOR B. D. Liaw, Assistant Director, Technical Review Division of TVA Projects, Office of Special Programs Gary G. Zech, Assistant Director, Inspection Programs,
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| FROM:
| | V JUL 2 2 U37 Tennessee Valley Authority MTTN: Mr. S. A. White Manager of Nuclear Power 6N 38A Lookout P' ace 1101 Market Street Chattanooga, TN 37402-2801 Gentlemen: |
| Division of TVA Projects, Office of Special Progre.ms SUBJECT: ASCO SOLEN 0ID VIOLATION 86-42-01
| | SUBJEC INSPECTION REDORT NOS. 50-327/86-42 AND 50-328/86-42 l |
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| Two examples of Violation 86-42-01 were cited in Inspection Report 86-42 pertaining to ASCO solenoid valves (one on seismic qualification, one on environmental qualification). These issues resulted from two unresolved items identified in Inspection Report 85-45 and later reviewed in Inspection Report '
| | We have completed our evaluation of your April 6, 1987 response tc our February 26, 1987 letter concerning Violation 50-327,328/86-42-01 (Example 2). It has been. concluded that your reason for cenial is valid based on the following additional discussions and information: |
| 86-01. These items were upgraded to violations in Inspection Report 86-4 TVA responded to the violation on October 24, 1986, by admitting the first example of 86-42-01 pertaining to the seismic qualification, but denied the second example pertaining to environmental qualification. A request for technical assistance was sent from myself to Brian Grimes on December 5, 1986, to evaluate the environmental qualification issues addressed in Report 86-42 as Violation 86-42-01 and Unresolved Item 86-42-0 George Hubbard evaluated these issues during his inspection reported in Inspection Report 86-70 on December 12, 1986, and addressed these issues in a Grimes memorandum dated January 16, 1987, which concluded that the violation was valid. We issued a response to TVA's denial of October 24, 1986, based on the January 16, 1987, Grimes' memorandum refuting TVA's denial an February 26, 1987 TVA on April 6,1987, again denied the violation. George Hubbard has recently discussed the second denial with TVA. In light of this second denial, please evaluate this EQ issue from a technical standpoint and determine if TVA's denial is valid based on the NRC's EQ polic If you consider that TVA's denial is not valid, please prepare a draft response to TVA that represents how you believe the NRC should respond to this denia It is requested that you respond to this memorandum by May 22, 1987, to support completion of Sequoyah inspection activitie ORIGINAL. SIGNED BY
| | 1) The information presented in your April 6, 1987 respons ) Information obtained during the NRC inspection in April 1987 (87-22). |
| , KENNET" 9 VRR | | |
| 'l M Gary G. Zech
| | 3) Discussions with ASCO concerning the subject valv ) Discussions with Franklin Research Center concerning ASCO solenoid valve Accordingly, we are withdrawing Example 2 of the subject violatio We do, however, wish to clarify a statement made on page 2 of the enclosure to your April 6,1987 response. In paragraph 2 of Item 1, TVA makes the statement that the ASCO NP8316 solenoid qualification maintenance data sheets (QMDSs) |
| | and to 'que values for the valve bonnet-body screws were reviewed as part of the NRC EQ maintenance inspection conducted Deceiaber 8-12, 1987. This is incorrect, in that the NRC inspectors did not look at any ASCO qualification binders, QMDds, or valve bonnet-body screw torque values duri.ng the inspectio The only solenoid valve data reviewed during the inspection were for non-ASCO valve While this has no bearing on the above conclusion, it siauld be clarified for the recor We appreciate your cooperation in this matte |
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| Enclosures: Inspection Report 86-42 TVA first denial . Grimes memorandum RII response to TVA TVA second denial
| | Sincerely, OfflGINAL SIGNED By q GARY G. ZECH Gary G. Zech, Assistant Director, Inspection Programs D' vision of TVA Projects Office of Special Projects cc: (See page 2) |
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| l cc w/o encls: (See page 2)
| | 8707POO301 870722 PDR ADOCK 05000327 G PDR ND |
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| /H. L.'Abercrombie, Site Director >
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| .Sequoyah Nuclear Plant
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| / A. Kirkebo, Acting Director, t .d.NuclearEngineering
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| 'L. Gridley, Director Nuclear Safety and Licensing | | , |
| /M. R. Harding, Site Licensing Manager bec w/o encls:
| | Tennessee Valley Authority 2 i |
| /). G. Keppler, OSP
| | cc: LH. L. Abercrombie, Site Director Sequoyah Nuclear Plant IK A. Kirkebo, Director, |
| /S. D. Ebneter, OSP | | ' Nuclear Engineering 14. L. Gridley, Director Nuclear Safety and Licensing d4 R. Harding, Site Licensing Manager bec: Of G. Keppler, OSP i 1&. D. Ebneter, OSP LR A. Iwolinski, OSP LB. D. Liaw, OSP L& D. Richardson, OSP 01A t.Sc R. Connelly,/RII K. P..Barr, 0$P (NRC Resident Inspector NRC Document Control Desk State of Tennessee |
| /J.A.Zwolinski,OSP
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| /S. D. Richardson, OSP
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| /S. R. . Connelly, OIA K. P. Barr, OSP/RII yNRCResidentInspector-NRC Document Control Desk State of Tennessee
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M4461999-10-20020 October 1999
Forwards Rev 8 to Sequoyah Nuclear Plant Physical Security/ Contingency Plan, IAW 10CFR50.54(p).Encl Withheld,Per 10CFR73.21
ML20217J4151999-10-15015 October 1999
Forwards Request for Addl Info Re Util 990624 Application for Amend of TSs That Would Revise TS for Weighing of Ice Condenser Ice Baskets
05000327/LER-1999-002, Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project1999-10-15015 October 1999
Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project
ML20217G1141999-10-0707 October 1999
Responds to from P Salas,Providing Response to NRC Risk Determination Associated with 990630 Flooding Event at Sequoyah Facility.Meeting to Discuss Risk Determination Issues Scheduled for 991021 in Atlanta,Ga
ML20217B2981999-10-0606 October 1999
Discusses Closeout of GL 92-01,rev 1,suppl 1, Reactor Vessel Integrity, for Sequoyah Nuclear Plant,Units 1 & 2. NRC Also Hereby Solicits Any Written Comments That TVA May Have on Current Rvid Data by 991101
ML20217B8431999-10-0505 October 1999
Requests NRC Review & Approval of ASME Code Relief Requests That Were Identified in Plant Second 10-yr ISI Interval for Both Units.Encl 3 Provides Util Procedure for Calculation of ASME Code Coverage for Section XI Nondestructive Exams
IR 05000327/19990041999-10-0101 October 1999
Ack Receipt of Providing Comments on Insp Repts 50-327/99-04 & 50-328/99-04.NRC Considered Comments for Apparent Violation Involving 10CFR50.59 Issue
ML20217C7101999-10-0101 October 1999
Forwards Response to NRC 990910 RAI Re Sequoyah Nuclear Plant,Units 1 & 2 URI 50-327/98-04-02 & 50-328/98-04-02 Re Ice Weight Representative Sample
ML20212J5981999-10-0101 October 1999
Forwards SE Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plnat,Unit 1
ML20212M1081999-09-29029 September 1999
Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program
ML20217A9451999-09-27027 September 1999
Forwards Insp Repts 50-327/99-05 & 50-328/99-05 on 990718- 0828.One Violation Identified & Being Treated as Non-Cited Violation
ML20216J9351999-09-27027 September 1999
Responds to NRC Re Violations Noted in Insp Repts 50-327/99-04 & 50-328/99-04.Corrective Actions:Risk Determination Evaluation Was Performed & Licensee Concluded That Event Is in Green Regulatory Response Band
ML20212F0751999-09-23023 September 1999
Forwards SER Granting Util 981021 Request for Relief from ASME Code,Section XI Requirements from Certain Inservice Insp at Sequoyah Nuclear Power Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii)
ML20212F4501999-09-23023 September 1999
Forwards Amends 246 & 237 to Licenses DPR-77 & DPR-79, Respectively & Ser.Amends Approve Request to Revise TSs to Allow Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters
ML20212M1911999-09-21021 September 1999
Discusses Exercise of Enforcement Discretion Re Apparent Violation Noted in Insp Repts 50-327/99-04 & 50-328/99-04 Associated with Implementation of Procedural Changes Which Resulted in Three Containment Penetrations Being Left Open
ML20211Q0311999-09-10010 September 1999
Requests Written Documentation from TVA to Provide Technical Assistance to Region II Re TS Compliance & Ice Condenser Maint Practices at Plant
ML20216F5441999-09-0707 September 1999
Provides Results of Risk Evaluation of 990630,flooding Event at Sequoyah 1 & 2 Reactor Facilities.Event Was Documented in Insp Rept 50-327/99-04 & 50-328/99-04 & Transmitted in Ltr,
ML20211N5681999-09-0101 September 1999
Submits Clarification of Two Issues Raised in Insp Repts 50-327/99-04 & 50-328/99-04,dtd 990813,which Was First Insp Rept Issued for Plant Under NRC Power Reactor Oversight Process Pilot Plant Study
ML20211G5881999-08-27027 August 1999
Submits Summary of 990820 Management Meeting Re Plant Performance.List of Attendees & Matl Used in Presentation Enclosed
ML20211F8891999-08-25025 August 1999
Forwards Sequoyah Nuclear Plant Unit 1 Cycle 9 Refueling Outage, Re Completed SG Activities,Per TSs 4.4.5.5.b & 4.4.5.5.c
ML20211A1851999-08-16016 August 1999
Forwards Proprietary TR WCAP-15128 & non-proprietary Rept WCAP-15129 for NRC Review.Repts Are Provided in Advance of TS Change That Is Being Prepared to Support Cycle 10 Rfo. Proprietary TR Withheld,Per 10CFR2.790
ML20210V1471999-08-13013 August 1999
Forwards Insp Repts 50-327/99-04 & 50-328/99-04 on 990601- 0717.One Potentially Safety Significant Issue Identified.On 990630,inadequate Performance of Storm Drain Sys Caused Water from Heavy Rainfall to Backup & Flood Turbine Bldg
ML20211A1921999-08-12012 August 1999
Requests Proprietary TR WCAP-15128, Depth-Based SG Tube Repair Criteria for Axial PWSCC at Dented TSP Intersections, Be Withheld from Public Disclosure Per 10CFR2.790
ML20210Q5011999-08-0505 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006 at Sequoyah Nuclear Plant. Sample Registration Ltr Encl
ML20210L4291999-08-0202 August 1999
Forwards Sequoyah Nuclear Plant Unit 2 Cycle 9 12-Month SG Insp Rept & SG-99-07-009, Sequoyah Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept. Repts Submitted IAW TS 4.4.5.5.b & TS 4.4.5.5.c
ML20210L1611999-07-30030 July 1999
Forwards Request for Relief RV-4 Re ASME Class 1,2 & 3 Prvs, Per First ten-year Inservice Test Time Interval.Review & Approval of RV-4 Is Requested to Support Unit 1 Cycle 10 Refueling Outage,Scheduled to Start 000213
ML20210G5301999-07-28028 July 1999
Forwards Sequoyah Nuclear Plant Unit 2 ISI Summary Rept That Contains Historical Record of Repairs,Replacement & ISI & Augmented Examinations That Were Performed on ASME Code Class 1 & 2 Components from 971104-990511
ML20211B9661999-07-26026 July 1999
Informs That Sequoyah Nuclear Plant Sewage Treatment Plant, NPDES 0026450 Outfall 112,is in Standby Status.Flow Has Been Diverted from Sys Since Jan 1998
ML20210B2521999-07-14014 July 1999
Confirms 990712 Telcon Between J Smith of Licensee Staff & M Shannon of NRC Re semi-annual Mgt Meeting Schedule for 990820 in Atlanta,Ga to Discuss Recent Sequoyah Nuclear Plant Performance
ML20210J1091999-07-10010 July 1999
Submits Suggestions & Concerns Re Y2K & Nuclear Power Plants
ML20196K0381999-06-30030 June 1999
Provides Written Confirmation of Completed Commitment for Final Implementation of Thermo-Lag 330-1 Fire Barrier Corrective Actions at Snp,Per GL 92-08
ML20209E4071999-06-30030 June 1999
Forwards Insp Repts 50-327/99-03 & 50-328/99-03 on 990328- 0531.Violations Being Treated as Noncited Violations
ML20196J8261999-06-28028 June 1999
Forwards Safety Evaluation Authorizing Request for Relief from ASME Boiler & Pressure Vessel Code,Section XI Requirements for Certain Inservice Inspections at Sequoyah Nuclear Plant,Units 1 & 2
ML20196G7881999-06-22022 June 1999
Informs NRC of Changes That Util Incorporated Into TS Bases Sections & Trm.Encl Provides Revised TS Bases Pages & TRM Affected by Listed Revs
ML20196G1801999-06-21021 June 1999
Requests Termination of SRO License SOP-20751-1,for Lf Hardin,Effective 990611.Subject Individual Resigned from Position at TVA
ML20195G1821999-06-0808 June 1999
Requests NRC Review & Approval of ASME Code Relief for ISI Program.Encl 1 Provides Relief Request 1-ISI-14 That Includes Two Attachments.Encl 2 Provides Copy of Related ASME Code Page
ML20195E9521999-06-0707 June 1999
Requests Relief from Specific Requirements of ASME Section Xi,Subsection IWE of 1992 Edition,1992 Addenda.Util Has Determined That Proposed Alternatives Would Provide Acceptable Level of Quality & Safety
ML20195E9311999-05-28028 May 1999
Informs of Planned Insp Activities for Licensee to Have Opportunity to Prepare for Insps & Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities
ML20195B3631999-05-21021 May 1999
Requests Termination of SRO License for Tj Van Huis,Per 10CFR50.74(a).TJ Van Huis Retired from Util,Effective 990514
ML20207A5721999-05-20020 May 1999
Forwards Correction to Previously Issued Amend 163 to License DPR-79 Re SR 4.1.1.1.1.d Inadvertently Omitted from Pp 3/4 1-1 of Unit 2 TS
ML20206Q8791999-05-13013 May 1999
Forwards L36 9990415 802, COLR for Sequoyah Nuclear Plant Unit 2,Cycle 10, IAW Plant TS 6.9.1.14.c
05000327/LER-1999-001, Forwards LER 99-001-00 Re Condition That Resulted in Granting of Enforcement Discretion,Per Failure of Centrifugal Charging Pump.Condition Being Reported IAW 10CFR50.73(a)(2)(i)(B) & (a)(2)(iv)1999-05-11011 May 1999
Forwards LER 99-001-00 Re Condition That Resulted in Granting of Enforcement Discretion,Per Failure of Centrifugal Charging Pump.Condition Being Reported IAW 10CFR50.73(a)(2)(i)(B) & (a)(2)(iv)
ML20206M9341999-05-10010 May 1999
Forwards Rept of SG Tube Plugging During Unit 2 Cycle 9 Refueling Outage,As Required by TS 4.4.5.5.a.ISI of Unit 2 SG Tubes Was Completed on 990503
ML20206K6271999-05-0606 May 1999
Requests Termination of SRO License for MR Taggart,License SOP-21336 Due to Resignation on 990430
ML20206J2061999-05-0404 May 1999
Requests Relief from Specified ISI Requirements in Section XI of ASME B&PV Code.Tva Requests Approval to Use Wire Type Penetrameters in Lieu of Plaque Type Penetrameters for Performing Radiographic Insps.Specific Relief Request,Encl
ML20209J0391999-04-27027 April 1999
Forwards Annual Radioactive Effluent Release Rept, Radiological Impact Assessment Rept & Rev 41 to ODCM, for Period of Jan-Dec 1998
ML20206C6541999-04-23023 April 1999
Forwards Response to NRC 990127 RAI Re GL 96-05 for Sequoyah Nuclear Plant,Units 1 & 2
ML20206C0841999-04-23023 April 1999
Forwards Insp Repts 50-327/99-02 & 50-328/99-02 on 990214-0327.No Violations Noted
ML20206B9591999-04-20020 April 1999
Responds to 990417 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in Unit 1 TS 3.1.2.2,3.1.2.4 & 3.5.2 & Documents 990417 Telephone Conversation When NRC Orally Issued NOED
ML20205S5891999-04-17017 April 1999
Documents Request for Discretionary Enforcement for Unit 1 TS LCOs 3.1.2.2,3.1.2.4 & 3.5.2 to Support Completion of Repairs & Testing for 1B-B Centrifugal Charging Pump (CCP)
1999-09-07
[Table view]
Category:NRC TO UTILITY
MONTHYEARML20062G7711990-11-20020 November 1990
Forwards Computer Printout of Generic & Plant Specific Info Contained in NRC Sims for Facility.Requests That Sims Printout Be Updated W/Actual or Projected Completion Dates for MPA Items within 90 Days of Receipt of Ltr
ML20062F5491990-11-16016 November 1990
Forwards Insp Repts 50-327/90-34 & 50-328/90-34 on 901006- 1105 & Notice of Violation
ML20217A5461990-11-14014 November 1990
Ack Receipt of 901026 Response to Violations Noted in Insp Repts 50-327/90-28 & 50-328/90-28.Implementation of Corrective Actions Will Be Examined During Future Insp
IR 05000327/19900221990-11-13013 November 1990
Ack Receipt of Addl Response to Violations Noted in Insp Repts 50-327/90-22 & 50-328/90-22.Corrective Actions Will Be Examined During Future Insps
ML20217A6051990-11-0909 November 1990
Forwards Augmented Insp Team Repts 50-327/90-36 & 50-328/90-36 on 901011-19.NRC Concludes That Multiple Failures of Main Steam Check Valves on 901008 Resulted from Inadequate Recognition & Correction of Deficiencies
ML20062F1831990-11-0808 November 1990
Advises That 901015 Rev 25 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable
ML20058E1111990-11-0202 November 1990
Grants 901023 Request for Extension of 60-day Reporting Requirement for Cycle 5 Radial Peaking Factor Limit Rept
ML20058F1141990-11-0101 November 1990
Forwards Insp Repts 50-327/90-32 & 50-328/90-32 on 900906- 1005 & Notice of Violation
IR 05000327/19900181990-10-31031 October 1990
Ack Receipt of Addressing Open Unresolved Items in Insp Repts 50-327/90-18 & 50-328/90-18
ML20058A8441990-10-11011 October 1990
Forwards Insp Repts 50-327/90-29 & 50-328/90-29 on 900827-31 & Notice of Violation
ML20062A0611990-10-0909 October 1990
Expresses Appreciation to Util for Prompt and Extensive Support Extended to NRC Following Fire at Inspector Home
ML20059N5811990-10-0202 October 1990
Forwards Insp Repts 50-327/90-31 & 50-328/90-31 on 900910-14.No Violations or Deviations Noted
ML20059N0711990-10-0202 October 1990
Requests Util to Provide within 45 Days of Receipt of Ltr Listing of All Commitments Made to Justify Restart of Plant
IR 05000327/19900231990-09-19019 September 1990
Confirms 900924 Mgt Meeting in Atlanta,Ga to Discuss ALARA Program & Weaknesses Noted in Insp Repts 50-327/90-23 & 50-328/90-23
ML20059F9071990-09-10010 September 1990
Ack Receipt of & Payment of Civil Penalty in Amount of $75,000,per NRC
ML20059H3741990-08-31031 August 1990
Forwards Insp Repts 50-327/90-26 & 50-328/90-26 on 900706-0805.Noncited Violations Noted
ML20059H0311990-08-30030 August 1990
Forwards Insp Repts 50-327/90-23 & 50-328/90-23 on 900625-29 & 0730.Weaknesses Noted.Util Encouraged to Provide Increased Mgt Attention to Radiological Controls to Assure That Significant Decline in ALARA Program Does Not Occur
ML20059H3531990-08-29029 August 1990
Forwards Insp Repts 50-327/90-27 & 50-328/90-27 on 900730-0803.No Violations or Deviations Noted
ML20056B4991990-08-21021 August 1990
Forwards Evaluation of Westinghouse Owners Group Bounding Analysis,Per Util Response to Bulletin 88-011, Pressurizer Surge Line Thermal Stratification
ML20058P8111990-08-0303 August 1990
Forwards Insp Repts 50-327/90-21 & 50-328/90-21 on 900709-13.No Violations or Deviations Noted
ML20056A4751990-07-26026 July 1990
Forwards Insp Repts 50-327/90-22 & 50-328/90-22 on 900606- 0705 & Notice of Violation.Nrc Decided Not to Hold Enforcement Conference or Propose Civil Penalty Because Significant Changes in Plant Mgt Occurred
ML20055H9261990-07-25025 July 1990
Advises That 900119 Response to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations, Acceptable
ML20055H8851990-07-25025 July 1990
Considers 900425 Request for Approval to Eliminate Site Local Recovery Ctrs Withdrawn.Review Terminated
IR 05000327/19900091990-07-20020 July 1990
Discusses SALP Repts 50-327/90-09 & 50-328/90-09 & Forwards Summary of 900530 SALP Meeting.Improvements Noted.Encourages Pursuance & Monitoring of Effectiveness of Corrective Actions
ML20055G5651990-07-20020 July 1990
Forwards Order Imposing Civil Penalty in Amount of $75,000, Per 900412 Notice of Violation.Violation Regards RHR Pump Deadheading.Requests Listed Info within 30 Days of Ltr Date
ML20055F9181990-07-19019 July 1990
Discusses Corrective Actions for Feedwater Control Problems During Unit 2,Cycle 3 Restart.Nrc Concludes That Feedwater Control Study Addresses Problems of feedwater-related Trips That Occurred in 1988 & 1989
ML20055G3381990-07-18018 July 1990
Advises of Closure of Review of Generic Ltr 83-28,Item 2.2.2 Re Vendor Interface for safety-related Components
ML20055F7971990-07-16016 July 1990
Advises That 900126 Response to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment, Acceptable.Documentation Re Implementation of Generic Ltr & Results of Programs Should Be Retained in Plant Records
ML20055D8231990-07-0303 July 1990
Advises That Util 890223,0512 & 900204 Responses to Generic Ltr 88-14 Re Instrument Air Sys Acceptable
ML20055D2611990-06-29029 June 1990
Requests Addl Info Re Alternative Testing of Reactor Vessel Head & Internals Lifting Rigs
ML20055H3901990-06-29029 June 1990
Forwards Insp Repts 50-327/90-20 & 50-328/90-20 on 900506-0606.No Violations or Deviations Noted
IR 05000327/19900141990-06-25025 June 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-327/90-14 & 50-328/90-14
ML20059M8551990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20248E2291989-09-28028 September 1989
Requests Addl Info Re Implementation of Suppl 3 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, within 30 Days of Ltr Receipt
IR 05000327/19890111989-09-26026 September 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-327/89-11 & 50-328/89-11
ML20248C1121989-09-22022 September 1989
Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $87,500 from Insp on 890506-0605
ML20248C7361989-09-21021 September 1989
Discusses Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 891211.Encl Ref Matl Requested by 891011 in Order to Meet Schedule
ML20247K3121989-09-14014 September 1989
Forwards Safety Evaluation Accepting ATWS Mitigation Sys for Plant.Atws Requirements Under Review to Determine to What Extent Tech Specs Appropriate
ML20247N8421989-09-14014 September 1989
Forwards Amend 9 to Indemnity Agreement B-82,reflecting Rev to 10CFR140,increasing Primary Layer of Nuclear Energy Liability Insurance
ML20247E6811989-09-0707 September 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-327/89-17 & 50-328/89-17
ML20247A9981989-08-31031 August 1989
Forwards Insp Repts 50-327/89-14 & 50-328/89-14 on 890424-28 & Notice of Violation.Insp Determined That Plant Personnel Failed to Follow Established Procedures for Assuring Proper Voltage on Shutdown Boards
ML20246L0061989-08-29029 August 1989
Advises That Util 890612 Response to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs, Acceptable
ML20246P6741989-08-29029 August 1989
Forwards Insp Repts 50-327/89-20 & 50-328/89-20 on 890717-20.No Violations or Deviations Noted
ML20246M5791989-08-25025 August 1989
Forwards Insp Repts 50-327/89-19 & 50-328/89-19 on 890706-0805 & Notice of Violation
ML20245K2111989-08-17017 August 1989
Confirms 890809 Withdrawal of Application for Permission to Dispose of Low Activity Radwaste in Sanitary Landfill,Per 10CFR20.302
ML20245K4311989-08-10010 August 1989
Forwards Insp Repts 50-327/89-18 & 50-328/89-18 on 890606-0705 & Notice of Violation
ML20245K8741989-08-10010 August 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-327/89-15 & 50-328/89-15
ML20245L3001989-08-0808 August 1989
Forwards Insp Repts 50-327/89-11 & 50-328/89-11 on 890626-30 & Notice of Violation
1990-09-19
[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
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V JUL 2 2 U37 Tennessee Valley Authority MTTN: Mr. S. A. White Manager of Nuclear Power 6N 38A Lookout P' ace 1101 Market Street Chattanooga, TN 37402-2801 Gentlemen:
SUBJEC INSPECTION REDORT NOS. 50-327/86-42 AND 50-328/86-42 l
We have completed our evaluation of your April 6, 1987 response tc our February 26, 1987 letter concerning Violation 50-327,328/86-42-01 (Example 2). It has been. concluded that your reason for cenial is valid based on the following additional discussions and information:
1) The information presented in your April 6, 1987 respons ) Information obtained during the NRC inspection in April 1987 (87-22).
3) Discussions with ASCO concerning the subject valv ) Discussions with Franklin Research Center concerning ASCO solenoid valve Accordingly, we are withdrawing Example 2 of the subject violatio We do, however, wish to clarify a statement made on page 2 of the enclosure to your April 6,1987 response. In paragraph 2 of Item 1, TVA makes the statement that the ASCO NP8316 solenoid qualification maintenance data sheets (QMDSs)
and to 'que values for the valve bonnet-body screws were reviewed as part of the NRC EQ maintenance inspection conducted Deceiaber 8-12, 1987. This is incorrect, in that the NRC inspectors did not look at any ASCO qualification binders, QMDds, or valve bonnet-body screw torque values duri.ng the inspectio The only solenoid valve data reviewed during the inspection were for non-ASCO valve While this has no bearing on the above conclusion, it siauld be clarified for the recor We appreciate your cooperation in this matte
Sincerely, OfflGINAL SIGNED By q GARY G. ZECH Gary G. Zech, Assistant Director, Inspection Programs D' vision of TVA Projects Office of Special Projects cc: (See page 2)
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Tennessee Valley Authority 2 i
cc: LH. L. Abercrombie, Site Director Sequoyah Nuclear Plant IK A. Kirkebo, Director,
' Nuclear Engineering 14. L. Gridley, Director Nuclear Safety and Licensing d4 R. Harding, Site Licensing Manager bec: Of G. Keppler, OSP i 1&. D. Ebneter, OSP LR A. Iwolinski, OSP LB. D. Liaw, OSP L& D. Richardson, OSP 01A t.Sc R. Connelly,/RII K. P..Barr, 0$P (NRC Resident Inspector NRC Document Control Desk State of Tennessee
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