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| | number = ML20138E539 | | | number = ML20138E539 |
| | issue date = 12/06/1985 | | | issue date = 12/06/1985 |
| | title = Responds to 851101 Ltr Re NRC Review of TVA Environ Qualification of Equipment.Plant Will Not Be Restarted Until Completion of NRC Review & Resolution of Issues in TVA-WESTEC Svcs,Inc Rept | | | title = Responds to Re NRC Review of TVA Environ Qualification of Equipment.Plant Will Not Be Restarted Until Completion of NRC Review & Resolution of Issues in TVA-WESTEC Svcs,Inc Rept |
| | author name = Palladino N | | | author name = Palladino N |
| | author affiliation = NRC COMMISSION (OCM) | | | author affiliation = NRC COMMISSION (OCM) |
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| | contact person = | | | contact person = |
| | document report number = NUDOCS 8512130473 | | | document report number = NUDOCS 8512130473 |
| | | title reference date = 11-01-1985 |
| | package number = ML19306B153 | | | package number = ML19306B153 |
| | document type = CORRESPONDENCE-LETTERS, NRC TO U.S. CONGRESS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, NRC TO U.S. CONGRESS, OUTGOING CORRESPONDENCE |
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| This responds to your letter of November 1, 1985 in which you expressed interest in NRC's review of TVA's Environmental Qualification (EQ) of equipment at Sequoyah Nuclear Plant. You may recall that TVA voluntarily shut down both Sequoyah units in August of this year because they concluded that compliance with 10 CFR 50.49 could not be demonstrated at those units. Since that time, the NRC staff has been in close communication with TVA regarding the status of their EQ program. This has included a review of the observations referred to in the TVA-WESTEC Services report (enclosed with your November 1 letter), a technical meeting with the licensee on September 16, 1985, and numerous phone calls among our technical staffs. On September 17, 1985, the Executive Director for Operations issued | | This responds to your letter of November 1, 1985 in which you expressed interest in NRC's review of TVA's Environmental Qualification (EQ) of equipment at Sequoyah Nuclear Plant. You may recall that TVA voluntarily shut down both Sequoyah units in August of this year because they concluded that compliance with 10 CFR 50.49 could not be demonstrated at those units. Since that time, the NRC staff has been in close communication with TVA regarding the status of their EQ program. This has included a review of the observations referred to in the TVA-WESTEC Services report (enclosed with your November 1 letter), a technical meeting with the licensee on September 16, 1985, and numerous phone calls among our technical staffs. On September 17, 1985, the Executive Director for Operations issued |
| ~ | | ~ |
| a request to TVA, under 10 CFR 50.54(f), for information relating to their EQ program and the qualification status of equipment at the Sequoyah facility. By letter dated November 1, 1985, TVA submitted its response to this letter. The NRC staff currently has this response under review. | | a request to TVA, under 10 CFR 50.54(f), for information relating to their EQ program and the qualification status of equipment at the Sequoyah facility. By {{letter dated|date=November 1, 1985|text=letter dated November 1, 1985}}, TVA submitted its response to this letter. The NRC staff currently has this response under review. |
| Prior to resuming operation, Sequoyah must be in compliance with the requirements of 10 CFR 50.49; and, therefore, the deficiencies identified in the TVA-WESTEC Services report must be resolved. In order to ensure the above, prior to restart of Sequoyah, the NRC staff will perform a thorough review and evaluation that includes the following: | | Prior to resuming operation, Sequoyah must be in compliance with the requirements of 10 CFR 50.49; and, therefore, the deficiencies identified in the TVA-WESTEC Services report must be resolved. In order to ensure the above, prior to restart of Sequoyah, the NRC staff will perform a thorough review and evaluation that includes the following: |
| -- A review of a representative number of TVA's 81 EQ packages for Sequoyah, to determine that they contain adequate documentation to demonstrate that the equipment is environmentally qualified. | | -- A review of a representative number of TVA's 81 EQ packages for Sequoyah, to determine that they contain adequate documentation to demonstrate that the equipment is environmentally qualified. |
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| TVA regaroing the status of their EQ program. This has included a review of the observations referred to in the TVA-WESTEC s_ '' | | TVA regaroing the status of their EQ program. This has included a review of the observations referred to in the TVA-WESTEC s_ '' |
| Services report (enclosed with your November i letter), a technical meeting with the licensee on September 16, 1985, and numerous phone calls among our technical staffs. On September 17, 1985, the Executive Director for Operations issued s a request to TVA, under 10 CFR 50.54(f), for information relating to their EQ program and the qualification status of < | | Services report (enclosed with your November i letter), a technical meeting with the licensee on September 16, 1985, and numerous phone calls among our technical staffs. On September 17, 1985, the Executive Director for Operations issued s a request to TVA, under 10 CFR 50.54(f), for information relating to their EQ program and the qualification status of < |
| equipment at the Sequoyah facility. By letter dated November 1, 1985, TVA submitted its response to this letter. The NRC staff currently har this response under review. | | equipment at the Sequoyah facility. By {{letter dated|date=November 1, 1985|text=letter dated November 1, 1985}}, TVA submitted its response to this letter. The NRC staff currently har this response under review. |
| Prior to resuming operation, Sequoyah must be in compliance with the requirements of 10 CFR 50.49; and, therefore, the s deficiencies identified in the TVA-WESTEC Services report must be resolved. In order to ensure the above, prior to restart of Sequoyah, the NRC staff will perform a thorough review and evaluation that includes the following: | | Prior to resuming operation, Sequoyah must be in compliance with the requirements of 10 CFR 50.49; and, therefore, the s deficiencies identified in the TVA-WESTEC Services report must be resolved. In order to ensure the above, prior to restart of Sequoyah, the NRC staff will perform a thorough review and evaluation that includes the following: |
| -- A review of a representative number of TVA's 81 EQ packages for Sequoyah, to determine that they contain adequate documentation to demonstrate that the ' | | -- A review of a representative number of TVA's 81 EQ packages for Sequoyah, to determine that they contain adequate documentation to demonstrate that the ' |
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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 U.S. CONGRESS
MONTHYEARML20247C3541989-03-17017 March 1989 Forwards Detailed Info Re Status of Implementation of TMI Action Plan Items at Listed Plants.Small Number of Action Items Still Need Resolution ML20151L3941988-04-14014 April 1988 Responds to ,Forwarding P Pierce Ltr Expressing Concern Re Cost of Util Operator Uniforms.Matter of Util Uniform Cost Outside Purview of NRC ML20149M6611988-02-22022 February 1988 Ack Receipt of Commenting on Commission & Offer to Suspend Subcommittee Request for Documents Upon Receiving Written Assurances That Commission Will Not Vote on Restart of Facility While Review Still Pending ML20206H8941987-03-31031 March 1987 Responds to Forwarding Constituent Ld Delius Ltr Expressing Concern That Safety Concerns Re TVA Nuclear Facilities Not Being Addressed Promptly by Nrc,Tva or Dept of Labor.Delius Concerns Included in TVA Tracking Sys ML20138E5391985-12-0606 December 1985 Responds to Re NRC Review of TVA Environ Qualification of Equipment.Plant Will Not Be Restarted Until Completion of NRC Review & Resolution of Issues in TVA-WESTEC Svcs,Inc Rept ML20128G3441985-05-10010 May 1985 Forwards Supplemental Info to Responses to 850326 Questions Re TVA Rept Concerning Pressure Monitoring Instrumentation. Fact Finding Team Recommended Enforcement Action to Be Taken Based on Inadequacies in TVA Procedures ML20140H8121985-05-0909 May 1985 Forwards Press Release 85-66 Re NRC Proposed Imposition of Civil Penalty in Amount of $112,500 Against TVA for Alleged Noncompliance W/Requirements Concerning 840419 Event When Tube Used to Insert Instrumentation Ejected 1989-03-17
[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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UNITED STATES NUCLEAR REGULATORY COMMISSION
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- CHAIRMAN December 6, 1985 The Honorable Marilyn Lloyd United States House of Representatives Washington, D. C. 20515
Dear Congresswoman Lloyd:
This responds to your letter of November 1, 1985 in which you expressed interest in NRC's review of TVA's Environmental Qualification (EQ) of equipment at Sequoyah Nuclear Plant. You may recall that TVA voluntarily shut down both Sequoyah units in August of this year because they concluded that compliance with 10 CFR 50.49 could not be demonstrated at those units. Since that time, the NRC staff has been in close communication with TVA regarding the status of their EQ program. This has included a review of the observations referred to in the TVA-WESTEC Services report (enclosed with your November 1 letter), a technical meeting with the licensee on September 16, 1985, and numerous phone calls among our technical staffs. On September 17, 1985, the Executive Director for Operations issued
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a request to TVA, under 10 CFR 50.54(f), for information relating to their EQ program and the qualification status of equipment at the Sequoyah facility. By letter dated November 1, 1985, TVA submitted its response to this letter. The NRC staff currently has this response under review.
Prior to resuming operation, Sequoyah must be in compliance with the requirements of 10 CFR 50.49; and, therefore, the deficiencies identified in the TVA-WESTEC Services report must be resolved. In order to ensure the above, prior to restart of Sequoyah, the NRC staff will perform a thorough review and evaluation that includes the following:
-- A review of a representative number of TVA's 81 EQ packages for Sequoyah, to determine that they contain adequate documentation to demonstrate that the equipment is environmentally qualified.
-- A physical inspection of selected equipment, to verify that the EQ documentation is applicable to the as-installed equipment.
-- A review of TVA's program for implementing the requirements of-10 CFR 50.49.
-- A review of TVA's program for maintaining the qualification of equipment during the life of the plant.
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Pending completion of this review, satisfactory resolution of the issues identified in the TVA-WESTI.C Services report, and a conclusion by the NRC staff that the plant can be operated in a safe manner, TVA will not restart either Sequoyah unit.
The Commission's current plans are to meet with TVA management and with the.NRC staff in January, 1986 regarding problems at TVA nuclear plants. NRC decisions to permit restart of the
. Sequoyah units would not be completed until after such meetings.
Sincerely,
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Nunzio'b. 'alladino O
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cwAinMAN December 6, 1985 The Honorable Jim Cooper United States House of Representatives Washington, D. C. 20515 ,
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Dear Congressman Cooper:
This responds to your letter of November 1, 1985 in which you N expressed interest in NRC's review of TVA's Environmental 4 Qualification (EQ) of equipment at Sequoyah Nuclear Plant. You may recall that TVA voluntarily shut down both Sequoyah units in -
l August of this year because they concluded that compliance with 10 CFR 50.49 could not be demonstrated at those units. Since that time, the NRC staff has been in close communication with ,
TVA regaroing the status of their EQ program. This has included a review of the observations referred to in the TVA-WESTEC s_
Services report (enclosed with your November i letter), a technical meeting with the licensee on September 16, 1985, and numerous phone calls among our technical staffs. On September 17, 1985, the Executive Director for Operations issued s a request to TVA, under 10 CFR 50.54(f), for information relating to their EQ program and the qualification status of <
equipment at the Sequoyah facility. By letter dated November 1, 1985, TVA submitted its response to this letter. The NRC staff currently har this response under review.
Prior to resuming operation, Sequoyah must be in compliance with the requirements of 10 CFR 50.49; and, therefore, the s deficiencies identified in the TVA-WESTEC Services report must be resolved. In order to ensure the above, prior to restart of Sequoyah, the NRC staff will perform a thorough review and evaluation that includes the following:
-- A review of a representative number of TVA's 81 EQ packages for Sequoyah, to determine that they contain adequate documentation to demonstrate that the '
equipment is environmentally qualified.
-- A physical inspection of selected equipment, to verify' that the EQ documentation is applicable,to the as-installed equipment.
-- A review of TVA's program for implementing the requirements of 10 CFR 50.49.
-- A review of TVA's program for maintaining the qualification of equipment during the life of the plant.
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. Pending completion-of this review, satisfactory resolution of
'the--issues identified in the'TVA-WESTEC Services report, and a conclusion.by'the NRC staff that the plant can be operated in a
- -l safe ma'nneti TVA will not restart either Sequoyah unit.
,The Commission's current plans are to meet with TVA management and with the NRC staff-in January, 1986 regarding problems at TVA nuclear plants.- NRC decisions'to permit restart ~of the Sequoyah qits would not be c'ompleted until after such meetings.
,c T' Sincerely, .
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Nunzio J. Palladino k
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