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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 Project stage: RAI 1999-10-15
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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
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October 15, 1999 l
Mr. J. A. Scalice
, President, TVA Nuclear and 1
Chief Nuclear Officer Tennessee Valley Authority ,
6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON CLARIFICATION OF ICE i CONDF.NSER ICE WEIGHING REQUIREMENTS FOR THE SEQUOYAH I NUCLEAR PLANT, UNIT 1 AND 2 (TAC NO. MA6065 AND MA6066) ,
Dear Mr. Scalice:
s !
On June 24,1999, Tennessee Valley Authority (licensee of Sequoyah Nuc!aar Plant (SON),
Units _1 and 2) submitted an application for amendment of the Technical Specifications (TS) that would revise the TS for the weighing of ice condenser ice baskets. The changes were identified as being consistent with a companion r'evision to the Improved Standard TS (ISTS), as submitted by the Nuclear Energy institute (NEI) Technical Specification Task Force to the U.S.
Nuclear Regulatory Commission staff on June 23,1999. The staff's review of the application has resulted in the enclosed request for additional information (RAl), as provided in the enclosure. Due to the simultaneous nature of the review of the SON and NEl submittals, the attached RAI also include requests related to the proposed changes to the ISTS.
As discussed with your staff on October 14,1999 we understand that you plan to respond to the enclosed RAI on or about December 17,1999.
Sincerely, Original signed by:
Ronald Hernan, Senior Project Manager Project Directorate 11-3 Division of Reactor Projects -l/II Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosure:
Request for AdditionalInformation I cc w/ enclosure: See next page 'i DISTRIBUTION:
" Docket File OGC ACRS SQN Rdg. C.Li PUBLIC S. Black R.' Hernan B. Clayton s i) k P. Fredrickson, Rll J.Hannon DOCUMENT NAME: G:\PDll-2\SQN\RAIA6065.wpd R. Mart;n W. Beckner See previous concurrence g
d To receive a copy of thle document. Indicate in the box: "C" = Copy without attachment /endosure 'E" - Copy wi9 attachment / enclosure
- N* = No copy OFFICE PDll-2\PM PDil-2\PM ,
PDll-2\LA TSB\BC DSSA PDil-2\SC_M NAME RMartin' RHemanM'BClayton* WBeckner* JHannon* SPetersodO DATE 9/30/99 10/14/99 ' 9/30/99 10/1 /99 9/30/99 10/ / f/99 OFFICIAL RECORD COPY
~
9910250000 991015 PDR ADOCK 05000327 iECRUCHHR CDP
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UNITED STATES s* j- NUCLEAR REGULATORY COMMISSION o e WASHINGTON, D.C. 20$5&0001
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October 15,1999 Mr. J. A. Scalice President, WA Nuclear and Chief Nuclear Officer Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON CLARIFICATION OF ICE
. CONDENSER ICE WElGHING REQUIREMENTS FOR THE SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 (TAC NO. MA6065 AND MA6066)
Dear Mr. Scalice:
On June 24,1999, Tennessee Valley Authority (licensee of Sequoyah Nuclear Plant (SON),
Units 1 and 2) submitted an application for amendment of the Technical Specifications (TS) that would revise the TS for the weighing of ice condenser ice baskets. The changes were identified as being consistent with a companion revision to the Improved Standard TS (ISTS), as submitted by the Nuclear Energy institute (NEI) Technical Specificatii n Task Force to the U.S.
Nuclear Regulatory Commission staff on June 23,1999. The staff's review of the application has resulted in the enclosed request for additionalinformation (RAl), as provided in the
. enclosure. Due to the simultaneous nature of the review of the SON and NEl submittals, the attached RAI also include requests related to the proposed changes to the ISTS.
As discussed with your staff on October 14,1999 we understand that you plan to respond to the enclosed RAI on or about December 17,1999.
Sincerely, tght .- WCAV Ronald W. Hernan, Senior Project Manager, Section 2 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosure:
Request for Additional Information cc w/ enclosure; See next page
REQUEST FOR ADDITIONAL INFORMATION REVISION OF ICE CONDENSER ICE WElGHING REQUIREMENTS SEQUOYAH NU_QLEAR PLANT DOCKET NOS. 50-327 and 50-328 Introduction The need for clarification of Technical Specifications (TS) for Ice Condenser Containment (ICC) plants was recognized in the letter from Mr. William Beckner, U.S. Nuclear Regulatory Commission (NRC), to Mr. James Davis, Nuclear Energy Institute, dated October 2,1998. The letter discussed issues recently identified related to licensee compliance with TS similar to the Westinghouse improved Standard Technical Specifications (ISTS) 3.6.15 " Ice Bed." These issues highlighted problems literally complying with the TS, ambiguities in the requirements, and in at least one case a TS with no apparent relationship to the design basis.
The letter from Mr. M.S. Tuckman, Duke Energy, to Mr. L.A. Reyes, NRC, dated October 21, 1998 indicated that the Ice Condenser Mini-Group (ICMG), a technical subgroup sponsored by the Westinghouse Owners Group, had recently decided to focus its efforts on the review and potential revision of ice condenser related TS in order to clarify them. ;
Proposed Revisions to Seauovah TS 4.6.5.1.d.2 and ISTS 3.6.15 Tennessee Valley Authority (TVA) has proposed the following revisions to TS 4.6.5.1.d.2 and Bases while retaining the requirement for " Weighing a representative sample of at least 144 ice ,
baskets." l
- 1. Individual Basket Wei.gh1 Reouirement - The requirement to " ..and verifying that each I
basket [ emphasis added] contains at least 1071 lbs of ice" is deleted and the 1071 lb limit now !
appears as an averaae 21-26 baskets.
)
i The safety analysis provided with the application does not provide a basis for deletion of this (1071) as a minimum requirement, except to note that it would provide consistency with a proposal also made in Technical Specification Task Force (TSTF)-335 for the Standard TS (STS). The staff is concerned that deletion of a clear and specific requirement that all baskets j be above a minimum value (required for accident analysis assumptions) may be an unsupported change to the TS since it would then allow basket weights to vary over an unspecified range about the average value. As noted in Insert B of the application, the objective of the weighing and the augmented 20-basket sample is to ensure that local below-weight zones that would allow early melt-out and bypass are not permitted. Please address how these concerns would be met with the proposed deletion of a minimum basket weight requirement.
- 2. Auamented 20 Basket Sample - The Sequoyah Units 1 and 2 (SON) TS 4.6.5.1.d.2 has been
. reformatted by moving the augmented 20 basket sampling requirement, (which requires weighing 20 additional baskets if one basket is found < [1071] Ibs) into a " Note" which appears at the beginning of the TS. For the STS, the augmented 20-basket sampling requirement is moved from the Bases into a " Note" which appears at the beginning of the TS.
ENCLOSURE
[ l The Note refers to th; striGhtforward averaging of 21 measured values of basket weights. At the end of the Note is the phrase: ". .at a 95% confidence level." Please address the l
appropriateness of this phrase for the averaging of 21 known values of ice basket weight.
I The augmented sampling requirement has also been modified such that, of the six baskets initially weighed per bay, only one additional 20-basket sample will be taken even if more than one of the six baskets is less than the required value. Discuss whether, in this case, the ,
average value for the bay is based on 21 or all 26 known basket weights. I
- 3. Definition of the Reoresentative Samole - Further requests for information on this topic are held in abeyance pending the results of review of TVA's letter of October 1,1999 to the NRC.
- 4. Calculation of total ice weiaht - A clause is added to the SON TS 4.6.5.1.d.2 on calculation of )'
the minimum total required ice weight that clarifies that this calculation is applicable to the beginning of each operating cycle. A similar clause is added to the STS.
This proposed change appears consistent with the purpose of the surveillance; to verify that adequate ice is available for the forthcoming cycle with appropriate allowance for sublimation and weighing uncertainties.
It is understood that during an outage, as-found and as-left weight sampling is performed and !
that, usually, several hundred baskets, including many from the crane wall rows, are serviced by having their ice weights increased. These serviced baskets would then appear to constitute a separate population from the remaining baskets since their weights may tend to be higher j and more uniform. Discuss the potential for this subset oi serviced baskets in the 144-basket i' representative sample to bias the average basket weight in an upward direction if as-left data is used. The response should also consider that the two crane-wall rows and the two containment-wall rows are represented to a greater proportional degree than the middle five rows in a .144-basket sample.
The response should also address the uncertainty in the estimate of the total amount of ice introduced by the interval since the most recent weight was obtained for the subset of frozen unweighable baskets.
- 5. Surveillance interval The proposed STS changed the surveillance frequency from every 9 months to every 18 months. However, the required amount of ice [1400] Ibs for each basket was not adjusted nor was an explanation provided to account for the longer sublimation period. Please discuss the basis for the acceptability of the longer interval.
. Bases
- 6. _SA h!! rap _tign A.l).p_wance The STS Bases SR 3.6.15.2 and the SON Bases 3/4.6.5.1 state that the average figure of (1400/1071) Ibs of ice per basket contains either a conservative allowance for ice loss through
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- .'sublimation which has been determined by plant specific analysis or a defined [15]% allowance.
The minimum weight figure of [2,721,600/2,082,024] Ibs of ice also contains an additional [1]%
conservative allowance to account for systematic error in weighing instruments. Provide the bases to justify the above allowance values of 15% and 1%. The response should include whether the sublimation allowance for a specific plant is based on the generic 15% value or on a plant-specific analysis (and if plant-specific, how it is determined). Also, discuss how the assumed value of 1% is reflected in the design basis and how it compares to plant operating experience.
- 7. Adiustment of Weiahts for Sublimation The proposed STS and SON Bases state that in the event that observed sublimation rates are equal to or lower than design prediction after three years of operation, the minimum ice basket !
weights may be adjusted downward. The proposed specificatior?s do not address responses if sublimation is observed to be higher than predicted. It appears that the future adjustment will only be biased in a downward direction. From the meeting with the owner's group on August 11, 1999,it is understood that the adjustment of the minimum ice basket weights being addressed would require an amendment to the license and TS, which would be subject to NRC review. I Given that a license amendment is required to make such an adjustment, why is the above statement on the future adjustment needed? -
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Mr. J. A. Scalice SEQUOYAH NUCLEAR PLANT l Tennessee Valley Authority cc:
Mr. Karl W. Singer, Senior Vice President- Mr. Pedro Salas, Manager Nuclear Operations Licensing and Industry Affairs Tennessee Valley Authority - Sequoyah Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN ' 37402-2801 Soddy Daisy. TN 37379 Mr. Jack A. Bailey Mr. D. L. Koehl, Plant Manager
' Vice President . . Sequoyah Nuclear Plant Engineering & Technical Services Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 6A Lookout Place Soddy Daisy, TN 37379 1101 Market Street -
Chattanooga, TN 37402-2801 Mr. Melvin C. Shannon Senior Resident inspector Mr. Masoud Bajestani Sequoyah Nuclear Plant Site Vice President : U.S. Nuclear Regulatory Commission Sequoyah Nuclear Plant 2600 Igou Ferry Road
' Tennessee Valley Authority Soddy Daisy, TN 37379 P.O. Box 2000 Soddy Daisy, TN 37379 Mr. Michael H, Mobley, Director TN Dept. of Environment & Conservation
. General Counsel Division of Radiological Health Tennessee Valley Authority 3rd Floor, L and C Annex ET 10H : 401 Church Street 400 West Summit Hill Drive Nashville, TN 37243-1532 Knoxville,TN 37902 County Executive Mr. N. C. Kazanas, General Manager- Hamilton County Courthouse
' Nuclear Assurance Chattanooga, TN 37402-2801 Tennessee Valley Authority SM Lookout Place
-1101 Market Street Chattanooga, TN 37402 2801
' Mr. Mark'J. Burzynski, Manager Nuclear Licensing Tennessee Valley Authority l 4X Blue Ridge .
1101 Market Street Chattanooga, TN 37402-2801