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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:EXTERNAL CORRESPONDENCE
MONTHYEARML20211B9661999-07-26026 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 ML20205H8891999-03-30030 March 1999 Forwards 1998 Tennessee Multi-Sector General Permit Storm Water Monitoring Rept for Sqn. Comments Re Manner in Which Rept Was Prepared,Provided ML20205B6461999-03-22022 March 1999 Forwards Underground Storage Tank (Ust) Permanent Closure Rept, on20,500-gallon Security Backup DG Underground Storage Tank Sys Located at Sequoyah Nuclear Plant.Sys Closed in Place Between 990217 & 23.Synopsis,listed ML20198H5121998-12-17017 December 1998 Resubmits Notification of Pcb Activity Form and Corrected Pcb Transformer Registration Form ML20197J9511998-12-0808 December 1998 Forwards Pcb Transformer Registration Form for TVA Snp,Units 1 & 2 ML20154P5241998-10-13013 October 1998 Forwards NPDES Discharge Monitoring Repts (DMR) for Third Quarter 1998.Two Changes to DMR Listed ML20151Z6431998-09-15015 September 1998 Forwards Air Permit Applications for Snp,Units 1 & 2, Lubrication Oil Sys Vapor Extractor Vents ML20151T1191998-09-0101 September 1998 Forwards Revised Flow Diagram & EPA Form 3510-2C Re NPDES Permit TN0026450 - ERCW Discharge ML20248L6211998-06-0202 June 1998 Forwards Signed Page 90 of Form 2C,permit Renewal Application,Containing Required Info Re Addl Contract Laboratory & Other Info Requested.W/One Oversize Drawing ML20198T3811998-01-21021 January 1998 Requests Permission to Move Front Insulator Saw,Certificate of Operation 4150-30700804-07C,from Present Location to Same Location as Back Mod Insulator Saw,Certificate of Operation 4150-30700804-06C ML20199J1531998-01-15015 January 1998 Forwards General Info & Form 2C Info Required for Renewal of Sequoyah NPDES Permit TN002650,which Expires on 980831 ML20198N3761997-10-17017 October 1997 Forwards Written Rept on Snp 971011 Event That Caused Total Residual Chlorine Excursion.Rept Follows Up 971017 Telcon Re Subj Matter ML20149K7471997-07-23023 July 1997 Submits Cancellation of Scheduled Demolition of Four Aercw Cooling Towers to Begin 970728 & End on 970831 ML20141H2761997-07-11011 July 1997 Forwards Demolition/Removal Permit Application for SQN Re Scheduled Demolition of Four Aercw Cooling Towers from 970728 to 0831 ML20078N9191994-11-0707 November 1994 Discusses Investigation Re Capcitors Installed in HDR Converters ML20070D8311994-06-29029 June 1994 Responds to NRC Questions Posed During Telcons & Provides Current Westinghouse Position on Containment & Accumulator Initial Temp Assumptions for Large Break LOCA Analysis. Current Accumulator Water Temp Assumed in Analysis 90 F ML20062N6361994-01-11011 January 1994 Discusses Water Storage at Cowanesque Reservoir Power Uprate Evaluation ML20198Q2011992-11-30030 November 1992 Conforms to Conditions & Limitations Specified in 49CFR173.422 for Excepted Radioactive Matl Instruments & Articles ML20086D9651991-11-13013 November 1991 Advises That Util Intends to Bury Polychlorinated Biphenyl Sediments,Containing Low Levels of Radioactivity,Onsite.Util Will Pursue NRC Approval Per 10CFR20.302.Requests Concurrence Re Disposal of Matl ML20029A2121991-01-30030 January 1991 Forwards Revised Page 18 to Toxicity Rept on Diffuser Element Contained in Recently Submitted Discharge Monitoring Rept ML20043A0371990-05-0808 May 1990 Forwards Document Outlining TVA Evaluation of Options for Preventing Damage to Fish & Aquatic Life from Plant Discharges,In Response to 900117 Order ML20042E0861990-04-0202 April 1990 Responds to Issues Noted During 891204-06 Compliance Sampling Insp.Corrective Actions:River Level Monitoring Sys Inspected at Least Twice Per Month & Diffuser Pond Bubbler Gauge Sys Inspected Once Per Wk ML19353B0531989-11-20020 November 1989 Discusses NPDES Polychlorinated Biphenyls (Pcb) Cleanup Plan.Status of Reclamation Efforts for Low Vol Waste Treatment Pond Provided.Pcb Sampling Grid Analytical Results Encl ML20246L8511989-08-30030 August 1989 Forwards Predictive Section 316(a) Demonstration for Alternative Winter Thermal Discharge Limit for Sequoyah Nuclear Plant,Chickamauga Reservoir,Tn ML20246F8521989-08-24024 August 1989 Documents Sampling Plan Quantifying Polychlorinated Biphenyls Concentrations in Plant Low Vol Waste Treatment Pond Sediment.Attendance List for 890811 Meeting Encl ML20246H0711989-08-22022 August 1989 Requests Concurrence to Allow Discharge of Nonradioactive Wastes Into Moccasin Bend Sewage Treatment Plant Via Sewer Line Recently Installed Between Plant Site & Soddy-Daisy. List of Quantities & Generation Frequencies Encl ML20246H4391989-08-15015 August 1989 Responds to Re Need for Permit to Dispose of Scum & Sludge Removed from Sewage Treatment Plant.Util Needs Only to Submit Description of Monitoring Program Used to Ensure Sludge Not Radioactive.Technical Instruction Encl ML20245J8321989-08-0909 August 1989 Forwards Renewal Applications for Certificates of Operation 4150-20199997-01C & 4150-20199997-03C ML20247J2711989-07-21021 July 1989 Forwards Chickamauga Reservoir 1988 Fisheries Monitoring Cove Rotenone Results. Util Plans to Relocate Block Nets at Uppermost Cove (Sewee Creek) to Obtain More Representative Sample from Outside Reservoir Drawdown Zone ML20246L3341989-07-12012 July 1989 Forwards Response to 890427 Request for Addl Info Re 890301 Permit Applications for Existing Air Pollution Sources - Supplemental Data.W/One Oversize Drawing ML20247R3601989-06-0202 June 1989 Forwards Response to Re Deficiencies Noted in Performance Audit Insp Conducted on 890329-31.Corrective Actions:Listed Activities Conducted or Scheduled to Improve Diffuser Flow Measurement,Calibr & Recordkeeping ML20245L1441989-04-27027 April 1989 Notifies That Discharge Serial Number 001,sewage Treatment Plant Effluent,Eliminated Per 880429 Engineering Rept. Written Approval to Cease Submission of Discharge Monitoring & Monthly Operation Repts for Sys Requested ML20245F0751989-04-26026 April 1989 Notifies That Discharge Serial Numbers 111 & 113 Sewage Treatment Plant Effluents Eliminated,Per 880429 Rept. Requests Written Approval to Cease Submission of Discharge Monitoring Repts & Monthly Operation Repts for Sys ML20245D0671989-04-18018 April 1989 Advises That Permit Application for Installation of Gasoline & Diesel Fuel Oil Tanks Submitted to County on 860513.On 860702,certificate Issued.Tanks Never Installed.Util Requests That Permit Not Be Renewed ML20244D5991989-04-10010 April 1989 Submits Followup to Performance Audit Insp Conducted on 890329-31.Monitoring Discontinued After 1985 Since No Changes Occurred in Plant Operations That Suggest Some Alteration of Chickamauga Reservoir Water Quality ML20235V4201989-03-0101 March 1989 Forwards Permit Applications for Listed Existing Sources at Plant ML20206M2181988-11-23023 November 1988 Confirms 881117 Conversation on Actions Taken Re Detection of Polychlorinated Biphenyls in Low Vol Waste Treatment Pond.Suggestion to Treat Pond Contents W/Chemicals to Facilitate Colloidal Sedimentation Offers Promise ML20205G5561988-10-25025 October 1988 Forwards Addl Info to Support Renewal of NPDES Permit TN0026450.Discharges Sampled During Aug,But Because of Intake Water Quality Problems,Reliable Data on Total Residual Chlorine Not Obtained ML20151V3661988-08-16016 August 1988 Confirms 880804 Telcon Between Util & Tennessee Div of Water Pollution Control Re Chickamauga Reservoir Temps.Telcon Informs That River Temps Upstream & Downstream Periodically Exceeded 86.9 Degrees F on 880801,02 & 03 ML20207E1091988-08-10010 August 1988 Comments on Draft State Permit 88-036 for Sewage Hold & Haul Operation at Plant,Per 880719 Request.Rhea County Should Be Changed to Hamilton County ML20196L3101988-06-30030 June 1988 Forwards Chickamauga Reservoir 1987 Fisheries Monitoring Cove Rotenone Results. Recommends That Sampling in Uppermost Cove Be Discontinued Because Data May Not Be Representative of Reservoir Fish Populations ML20150A8211988-06-29029 June 1988 Responds to Re Violations Noted in Insp Repts. Corrective Actions:Sewage Being Routinely Pumped from Sys & Hauled to Chattanooga Regional Sewage Treatment Facility to Minimize Potential for Noncompliances ML20155G7761988-06-13013 June 1988 Informs That Licensee No Longer Considering Relocating Fish from Diffuser Pond to Chickamauga Reservoir But Plans to Dispose Fish by Burial Onsite.Licensee Will Request Approval of Burial from Tennessee Div of Solid Waste Mgt ML20154P2701988-05-25025 May 1988 Notifies of Util Intent to Use Herbicides to Control Aquatic Weed Growth in Diffuser Pond,Yard Pond & Low Vol Waste Treatment Pond at Facility to Control Growth of Aquatic Weeds.Pertinent Info on Herbicides Encl ML20148L6921988-03-30030 March 1988 Notifies of Proposed Use of Sodium Bromide in Addition to Sodium Hypochlorite in ERCW Sys to Control Biofouling.Use of Bromide Reduces Total Residual Chlorine & Aids in Compliance W/Npdes Permit.Info on Products Being Considered Encl ML20235R6961987-10-0101 October 1987 Forwards EPA Forms 3510-1 & 3510-2C for Renewal of NPDES Permit TN0026450,including Description of Boron Sources & Discharge Points,List of Chemicals Added to Each Discharge & Description of Program to Control Microbiological Corrosion ML20235H9211987-07-0808 July 1987 Follows Up Re Investigation of Plant Impact on Dissolved Levels in Chickamauga Reservoir.Rhodamine WT Dye Study Conducted on 870615-16 Resulted in Dye Concentrations of Less than 10 Ppb at All Known Intakes in Survey Reaches ML20214T7761987-06-0202 June 1987 Requests Approval to Use Rhodamine WT Dye in Field Study in Chickamauga Reservoir in Vicinity of Underwater Dam (TRM 483.76) on 870615-16.Test Time Will Be Verbally Confirmed at Least 3 Days Prior to Actual Dye Injection ML20205Q5991987-03-31031 March 1987 Forwards Aquatic Environ Conditions in Chickamauga Reservoir During Operation of Sequoyah Nuclear Plant - Sixth Annual Rept (1986). Based on Cove Rotenone Sampling Since 1970,operation of Facility Had No Adverse Effect on Fish ML20209D3501986-08-29029 August 1986 Forwards Aquatic Environ Conditions in Chickamauga Reservoir During Operation of Sequoyah Nuclear Plant,Fifth Annual Rept (1985) & Apps.Jul 1985 Plan Alterations Decreased Phytoplankton & 200 Plankton Densities 1999-07-26
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Sd-dcP7 Q 50 - 39 2 t
H Westinghouse Energy Systems Box 3ss Electric Corporation PMgh Pensytvama 15230 0355 l
l June 29,1994 i
TVA 94-098 Ref: ~ 1) ET NRC-92 3695
- 2) ET-NRC-92-3699 Mr. Mark J. Burzynski, Manager Department of Nuclear Engineering Tennessee Valley Authority Sequoyah Nuclear Power Plant, DSC-A P. O. Box 2000 Soddy Daisy, TN 37379 Tennessee Valley Authority Sequoyah Units 1 and 2 Update on Containment and Accumulator Initial Temocrature Assumotions for LB-LOCA Analysis
Dear Mr. Burzynski:
References (1) and (2) previously provided the NRC with information concerning the effect on Large
. Break LOCA calculated Peak Cadding Temperature (PCT) of assumptions in Containment air and Accumulator water initial temperatures. Reference (2) provided a detailed explanation of the effects. - At -
that time, the sensitivity of PCT to accumulator water temperature for a range of water temperature from 90*F to 120*F was an increase of 49'F to 150*F in PCT. The Reference (2) letter was the subject of ;
subsequent NRC telecons regarding the effects. This letter will respond to NRC questions posed during i the telecons and provide the current Westinghouse position on this issue.
To assist in the selection of the accumulator water temperature for Sequoyah Units 1 & 2, Westinghouse has reviewed the LB LOCA analysis, and the current accumulator water temperature assumed in the
- analysis is 90'F.
Please contact M. E. Nissley (412-374-4303), Manager of Safeguards Analysis I, or C. M. Thompson =
(412-374-4409), if you have questions on this subject.
Very truly yours, M
D. R. Collier TVA Project Director l Domestic Customer Projects !
Attachment j
120CG8- .
mascto 9407120360 940629 PDR ADOCK 05000327
-P PDR ch\ ' i
n i
.i TVA 94-098 2 June 29,1994 l
l cc: R. H. Shell - Sequoyah Site . l D. M. Lafever - Sequoyah Site -!
K. P. Powers - Sequoyah Site i W. C. Ludwig - Sequoyah Site J D. F. Goetcheus - Chattanooga Office 1101 Market Street 1
U.S.; Nuclear Regulatory Commission
~ ATTN: Document Control Desk Washington, DC 20555 Attention: Mr. F. Orr, Reactor Systems Branch Office of Nuclear Reactor Regulation ;
I l
l l
i l
1 1
conscL-s
. - ~ - - - - - . - . . . _ - . - .
i i
[' /
Accumulator Water Temperature De change to the Westinghouse Large Break LOCA ECCS Evaluation Model Reported in Reference (3) and approved by the NRC in Reference (4) has had a significant effect on the sensitivity of PCT to accumulator water temperature. The change reported in Reference (3) concerned the fuel assembly I spacer grid model used in the BART and BASH versions of the Westinghouse 1981 Large Break l LOCA ECCS Evaluation Model (References 5 & 6). A logic error in the calculation of the spacer '
grid quenching and heat transfer models had sometimes resulted in erratic behavior of spacer grid quenching which could result in large changes to the calculated PCT when small changes were made to input assumptions. New sensitivity studies, using the corrected versions of the Reference (6)
Evaluation model have shown a much smaller sensitivity to accumulator water temperature than l reponed in Reference (2). In all cases the change in PCT is now less than 50'F when the' )
accumulator water temperature is allowed to vary from 90*F to 120*F. Since the sensitivity is now '
below the 10 CFR 50.46 threshold for determination of a significant change, Westinghouse believes that any change in analysis assumptions can be forward fitted to new analyses. To support this -
approach, this letter will provide guidance on implementing this change in future analyses. l Accumulator Water Temperature Analvala Assumption All LOCA analysis performed to satisfy Appendix K to 10CFR50 must meet the criteria of Appendix K part II, " Required Documentation", which states that: " Appropriate sensitivity studies shall be performed for each evaluation model, to evaluate the effect on calculated results of variations in I noding, phenomena assumed ira the calculation to predominata, including pump operation or locking, j and values of parameters over their applicable ranges. For items to which results are shown to be j sensitive, the choices made shall be justified." Traditionally, justification of the choice has required that the analysis value and the effect on calculated PCT over the'aup-*d range have an effect which is not significant, where significant is currently defined as greater than 50*F. Application of this i requirement to the choice of accumulator water temperature would result in a selection for which the !
effect of variations in water temperature during operation (8100% power) would not result m a H siguificant change in the calculated PCT (<50'F). 1 if the accumulators are in a location where the water temperature would be e=_p-M to trend with ;
conta nmaar air temperature, then an acceptable accumulator water temperature to use in Large Break 4 LOCA analyses could be based on,1) Tech-Spec maximum containmane air temperature, 2) maximum fan cooler exhaust temperature, or 3) the antimarad annualized average accumulator water temperature
(@ 100% power). Since the current sensitivity'of PCT to accumulator water temperature is about 1.3*F PCT for a l'F change in accumulator water temperature, the variation between the accumulator wasar temperature based on one of these definitions, and that used in the existing analysis should be less than 35'F (50*F/1.3*F PCT per l'F water temp). As an example, for the case of a plant with a Tech-Spec marimum air temperature of a 120*F and having a LOCA analysis which 1
- used 90*F as the minimum air temperature at 100% power, the range in air temperature is less than.
35'F. Aus an accumulator water temperature of 90'F or greater would be acceptable and could be justified in the analysis. If the locanon of the accumulators results in accumulator water temperatures which are either much houer or colder than the containmant average air temperature, then these values should be considered in the selection of the accumulator water temperature, keeping in mind
- that the uncertainty should be no greater than 35'F.
1 n , e ,
Since the effect of expected variations in accumulator water temperature have been shown to not have a significant effect on calculated PCT, Westinghouse believes it is not necessary to backfit -
assumptions for this parameter or provide a justification for continued operation. However, at the next large break LOCA analysis, using an Appendix K model, Westinghouse will request the utility to select a value to be used in the analysis.
Wsti h-- n---8=% on An=='=w Water T ==M F - :' =
Since this issue has previously been reported the NRC and this letter is in response to an NRC !
request, Westinghouse recommends that each utility review the currently assumed accumulator water temperature against expected temperatures during full power operation. If the variation between the accumulator water temperature based on one of the definitions given above, and that used in the -
existing analysis is less than 35'F (50*F/1.3*F PCT per l'F water temp) then no immediate action is necessary. If the current assumption is more than 35'F from one of the definitions given above, then it may be necessary to adjust the plant PCT to address the difference between the analysis ;
assumption and plant operating conditions.
Refueling Water Storage Tank (RWST) Tennperature 4
Due to a question regarding the effect of RWST temperature assumptions on the calculated results of large break LOCA analysis performed with the models of References (5) & (6), Westinghouse has performed sensitivity studies :n chaops in hWST temperature. RWST temperature affects both the ;
containmant spray temperature and pumped Safety injection temperatures. RWST temperature assumptions of 40*F, 80*F and 120*F were investigated with the result that the maximum PCT occurred when the RWST was at 40'F and the sensitivity seen for increasing RWST temperature was 4.16*F PCT /+ 1.0*F RW'iT. The ECCS model of Reference (6) uses the tachnical specification minimum RWST temperature for containmant spray and the nominal RWST temperature for the ;
pumped Safety Injecuon in the BASH reflood calculation, and this value can be set indapandantly l from the containment spray temperature used to calculate the containmant pressure. His input methodology applied to analyses performed with the Reference (6) models, results in a slightly <
conservative PCT calculation by some 2'F to 3*F. His input method has been applied consistently 1 to Reference (6) analyses when it was realized that changes in safety injection temperature could ;
result in either an increase or decrease in the calculated PCT, Since Westinghouse LOCA analysis performed to satisfy 10 CFR 50.46 and Appendix K to 10 CFR i 50 have historically used the miaimum RWST temperature in the analysis as one of the features riaadad to satisfy Appendix K to 10 CFR 50, there is no need to change the current modeling and no need to modify current analysis calculated PCTs.
Containannt Air Tensparatore Since the issuance of Reference (2) there has been no change in the Large Break LOCA PCT ret ponse to this parameter. Derefore, Westinghouse feels that the current modeling assumptions of using the mininmm containmane air temperature associated with 100% power is acoptable and will not change current practice, i
CONCLUSION ne sensitivity to accumulator water temperature reported in Reference (2) . has been found to be overly conservative based on new studies using the corrected model of Reference (4). Since the effect
)
of accumulator water temperature on calculated PCT is now less than the significance threshold set by 10 CFR 50.46, Westinghouse believes that this issue can be addressed by a forward fit use of the utility supplied accumulator water temperature at the next analysis. De sensitivity to RWST *
-) i
..v- _m. - . . . . ., , _ . , - _ . , . _ , ,
4
- , temperature has been determined and found to have a negligibl2 effect on calculated PCT. Therefora, ,
- Westinghouse will forward fit the utility selected' accumulator water temperature to new analyses performed with the models of Reference (5) or (6). t t
9 I
f
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l 1
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i
References
- 1. Letter ET-NRC-92-3695, N. J. Liparulo @ to U. S. Nuclear Regulatory Commission, "10CFR21 Interim Report: LOCA Contamment Initial Temperature Assumption", April 30, 1992.
- 2. Letter ET-NRC-92-3699, N. J. Liparuto @ to U. S. Nuclear Regulatory Commission, "Results of Technical Evaluation of Contamment Initial Temperature Assumptions for Large ;
Break Loss of Coolant Accident Analysis", June 1,1992.
- 3. Letter ET-NRC-92-3787, N. J. Liparulo @ to U. S. Nuclear Regulatory Commission,
" Notification of Changes to the Westinghouse Large Break LOCA ECCS Evaluation Model",
December 22,1992.
- 4. Letter Ashok C. Thadani (NRC) to N. J. Liparuto @, "Acces.sce for Referencing of Licensing Topical Report, WCAP-10484, Addendum 1, " Space Grid Heat Transfer Effects During Reflood" (TAC M85295), July 07,1993.
- 5. WCAP-9561-P-A, w/ Addenda (Proprietary) and WCAP-9562-A, w/Addanda (Non-Proprietary), Young, M.Y., "BART-A1: A Computer Code for the Best Eatimara Analysis of
- 6. WCAP-10266-P-A, Revision 2 (Proprietary), WCAP-10267-A, Revision 2 (Non-Proprietary),
Besspiata, J.J., et al, _"1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code," March 1987.
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