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| {{#Wiki_filter:~I | | {{#Wiki_filter:~I Westinghouse Energy Systems Box 355 Electric Corporation Pittsburgh Pennsylvania 15230-0355 July 25, 1994 VRA-94-079 Ref: 1) ET-NRC-92-3695 |
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| Westinghouse Energy Systems Box 355 Electric Corporation Pittsburgh Pennsylvania 15230-0355 July 25, 1994 VRA-94-079 Ref: 1) ET-NRC-92-3695 | |
| : 2) ET-NRC-92-3699 Mr. R. F. Saunders Vice President - Nuclear Operations Virginia Power Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, Virginia 23060 Virginia Power Surry Units 1 and 2, North Anna Units 1 and 2 Update on Containment and Accumulator Initial Temperature Assumptions for LB-LOCA Analysis | | : 2) ET-NRC-92-3699 Mr. R. F. Saunders Vice President - Nuclear Operations Virginia Power Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, Virginia 23060 Virginia Power Surry Units 1 and 2, North Anna Units 1 and 2 Update on Containment and Accumulator Initial Temperature Assumptions for LB-LOCA Analysis |
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| ' performed with the models of Reference (5) or (6). | | ' performed with the models of Reference (5) or (6). |
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| : 1. Letter ET-NRC-92-3695, N. J. Liparulo 00 to U. S. Nuclear Regulatory Commission, "10CFR21 Interim Report: LOCA Containment Initial Temperature Assumption", April 30, 1992. | | : 1. Letter ET-NRC-92-3695, N. J. Liparulo 00 to U. S. Nuclear Regulatory Commission, "10CFR21 Interim Report: LOCA Containment Initial Temperature Assumption", April 30, 1992. |
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| Besspiata, J .J., et al, " 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code," March 1987. | | Besspiata, J .J., et al, " 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code," March 1987. |
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| VRA-94-079 2 July 25, 1994 cc: M. L. Bowling C. B. Candee W L. M. Girvin E. W. Harrell M. R. Kansler M. L. Loftis J. P. O'Hanlon J. A. Price L. H. Roberts W J. A. Stall R. M. Berryman KL. Basehore D. A. Heacock S. R. Harms M. D. Crist D. M. Olson U.S. Nuclear Regulatory Commission ATfN: Document Control Desk Washington, DC 20555 Attention: Mr. F. Orr, Reactor Systems Branch Office of Nuclear Reactor Regulation 0088GL-11}} | | VRA-94-079 2 July 25, 1994 cc: M. L. Bowling C. B. Candee W L. M. Girvin E. W. Harrell M. R. Kansler M. L. Loftis J. P. O'Hanlon J. A. Price L. H. Roberts W J. A. Stall R. M. Berryman KL. Basehore D. A. Heacock S. R. Harms M. D. Crist D. M. Olson U.S. Nuclear Regulatory Commission ATfN: Document Control Desk Washington, DC 20555 Attention: Mr. F. Orr, Reactor Systems Branch Office of Nuclear Reactor Regulation 0088GL-11}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20212J9101999-10-0101 October 1999 Forwards SE Accepting Licensee 990916 & 27 Relief Requests IWE-3 for Plant.Se Addresses Only IWE-3 Due to Util Urgent Need for Relief.Requests IWE-7 & IWE-8 Will Be Addressed at Later Date ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20211N2531999-09-0808 September 1999 Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit 2.Informs That NRC Offers No Objection to Requested Use of Rods in Reconstituted Fuel Assembly.Se Supporting Request Encl ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211J2211999-08-31031 August 1999 Approves Request to Remove Augmented ISI (Aii) Program for RCS Bypass Lines from North Anna Licensing Basis.Se Re Request to Apply LBB to Eliminate Augmented Insp Program on RCS Bypass Lines Encl ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML20211B3871999-08-17017 August 1999 Requests Permission to Routinely Discharge from SW Reservior to Waste Heat Treatment Facility Under Existing Vpdes Permit Through Outfalls 108 & 103.Discharges Are Scheduled to Commence on 990907,due to High Priority Placed on Project ML20210T0671999-08-13013 August 1999 Informs of Completion of Review of Proposed Revs of Schedule for Withdrawal of Rv Surveillance Capsules Submitted by VEPCO on 981217.Approves Proposed Revs.Forwards Safety Evaluation ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210N2921999-08-0505 August 1999 Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl 1999-09-08
[Table view] Category:EXTERNAL CORRESPONDENCE
MONTHYEARML20211B3871999-08-17017 August 1999 Requests Permission to Routinely Discharge from SW Reservior to Waste Heat Treatment Facility Under Existing Vpdes Permit Through Outfalls 108 & 103.Discharges Are Scheduled to Commence on 990907,due to High Priority Placed on Project ML20196G2211999-06-21021 June 1999 Forwards Licensee Sampling & Testing Obligations Re Vpdes Permit VA0052451 Reissuance Application.Details of Requests for Sampling & Testing Waivers,Included ML20195J1391999-06-11011 June 1999 Submits Addl Info as Addendum to Original Application Which Proposed Use of Three Chemicals in Bearing Cooling Tower at North Anna Power Station,Per Reissuance of Vpdes Permit ML18152A4741999-05-19019 May 1999 Forwards Completed Registration Form for Renewal of ASTs at Surry Nuclear Power Station,Iaw Section 9VAC 25-91-100.F ML20206M7921999-05-0707 May 1999 Advises That Vepc Is Proposing to Use Three Chemicals in Bearing Cooling Tower at Naps,That Were Not Addressed in Licensee Last Application for Reissuance of Vpdes Permit ML18152B5991999-01-0808 January 1999 Confirms That Util Procedure for Tracking low-level Radiologically Contaminated Asbestos Waste (Rcaw),Acceptable for Maintaining Compliance with Natl Emissions Stds for Hazardous Air Pollutants (Neshap) Regulations ML20196H6431998-12-0303 December 1998 Informs That Util Is Seeking Approval to Discharge Chlorinated Blowdown from Bearing Cooling Tower for More than 2 H Per Unit as Specified in Special Condition 10 of Vpdes Permit.Meeting During Wk of 981214,requested ML20153G0131998-09-22022 September 1998 Requests Approval for Extended Compliance Schedule for Specific Provisions of Part III (9 VAC25-91-130,Pollution Prevention Requirements) for North Anna Nuclear Power Station ML18153A2671998-09-22022 September 1998 Requests Approval for Extended Compliance Schedule for Specific Provisions of Part III (9 Vac 25-91-130,Pollution Prevention Requirements) for Surry Nuclear Power Station ML18152B8171998-05-18018 May 1998 Discusses Results of Data Contained in Discharge Monitoring rept-QA (Dmr/Qa) Dtd 980114 ML20217Q7691998-05-0404 May 1998 Forwards Revised Application for Exclusionary General Permit for NAPS as Requested by D Vaughan in ML18153A2161998-01-23023 January 1998 Notifies That Plant Has Not Received Copy of Waste Shipment Record,Signed by Owner or Operator of Designated Waste Disposal Site within 35 Days Since Waste Was Shipped off- Site & Will Not Receive in 45 Days ML20198P8791998-01-12012 January 1998 Submits Application for Exclusionary General Permit for Plant ML20203H6111997-12-15015 December 1997 Forwards Application for General Storm Water Permit for Construction Activity at Naps.Local Government Ordinance Form,Pink Copy of Permit Application Fee Form & Copy of Check for Application,Encl ML20198P2871997-10-29029 October 1997 Requests That Vpdes Permit Be Amended to Reflect That Three Small Package Sewage Treatment Plants Were Permanently Removed from Svc ML20210G9721997-07-22022 July 1997 Submits Proposal to Pressure Test Piping within 10 Days Prior to Normal Fuel Oil Unloading Into Ast,Beginning No Later than 980101 ML20138B3381997-04-23023 April 1997 Provides Info to Support Proposal to Perform Annual Pressure Testing as Method of Leak Detection for Underground Line That Runs from Loading Area 5,000 Barrel Aboveground Storage Tank ML18153A1171997-03-19019 March 1997 Discusses Discharge Monitoring report-quality Assurance (DMR-QA) Results for VA Power Facilities ML18153A1111997-02-14014 February 1997 Confirms 970214 Telcon Re Location of Radiologically Contaminated Asbestos Waste Shipment S-96-1005 ML20149M8131996-12-0505 December 1996 Submits Conditions Which Are Part of 961202 Approval of Temporary Conditional Use Permit Which Allows Construction of Temporary ISFSI or Dry Cask Storage as Listed ML20101R2521996-04-10010 April 1996 Responds to Unacceptable Results Noted in Discharge Monitoring rept-QA Rept for North Anna Power Station (Permit VA0052451) & Yorktown Power Station (Permit VA0004103) ML20101J0511996-03-21021 March 1996 Provides Notice of Intent to Increase Amount of Reverse Osmosis Reject Water Discharged at Outfall 020 ML18151A1871996-03-20020 March 1996 Forwards Application for Reissuance of Vpdes Permit VA0004090 for Plant.W/One Oversize Map ML18153A5301996-03-18018 March 1996 Confirms That Procedure for Tracking low-level Radiologically Contaminated Asbestos Waste Acceptable for Maintaining Compliance W/Natl Emissions Stds for Hazardous Air Pollutants Regulations ML20100B9061996-01-24024 January 1996 Submits Annual Statement Verifying That Each Spillway Gate Operated at Least Once During Twelve Months Preceding Annual Insp by Ferc,Per 18CFR12.44(b)(2).Main Dam'S Five Spillway Gates Satisfactorily Tested as Specified on Attached Form ML18153A5561995-12-11011 December 1995 Requests Approval for Proposed Minor Change in Nature of Internal Discharge at Plant ML18153A6821995-11-29029 November 1995 Responds to 951114 Lab & Technical Insps at Plant on 950928. Submits Actions Taken to Address Items Noted During Insp & Reflected in Lab Rept ML18153A6721995-11-22022 November 1995 Requests That Vmrc Permit 92-1347 Be Extended to Allow Continued Maint Dredging Activity in Future ML18153A7801995-10-10010 October 1995 Responds to Concerns Re Leak Detection Sys in Facilities in Jurisdiction ML18153A7461995-08-30030 August 1995 Notifies of Minor Change in Discharge or Mgt of Pollutants at Surry Power Station ML20087L3411995-08-21021 August 1995 Notifies of Minor Change in Discharge or Mgt of Pollutants at Plant ML18153A7311995-08-0909 August 1995 Forwards Mixing & Dilution of Surry Nuclear Power Plant Cooling Water Discharge Into James River. ML18152A4011995-05-11011 May 1995 Responds to Telcons W/Eh Greene of VA Power'S Air Quality E Dept Re Use of Methylene Chloride in Paint Shop of Surry Power Station.Requests Confirmation That Painting Operation Exempt from Toxics Regulations ML20083K7181995-05-0404 May 1995 Forwards Application for Reissuance of Vpdes Permit for North Anna Power Station W/Addl Data Requested by ML18153A8081995-04-28028 April 1995 Provides Comments on EPA Pr Re Criteria for Certification & Determination of Waste Isolation Pilot Plant Compliance W/ Environ Standards for Mgt & Disposal of SF,high-level & Transuranic Radwastes.Guidance Re Categorization Needed ML18153A7921995-04-12012 April 1995 Submits Comments Re Proposed Revs to Guidance Provided to Federal Agencies on Radiation Protection ML20080J9181995-02-22022 February 1995 Submits Annual Statement Verifying That Each Spillway Gate Has Been Operated at Least Once During Twelve Months Preceeding Annual Insp by FERC Regional Engineer ML20080K8561995-02-22022 February 1995 Submits Notification for Spillway EDG Corrective Maint & Start Failure for Plant Hydroelectric Project ML18153B2351995-02-17017 February 1995 Informs of Receipt of NOV in Ref to Dec 1994 Excursion of Total Suspended Solids Limitations of Vpdes Permit for Plant ML20078M1481995-02-0808 February 1995 Discusses Series of Problems at Sewage Treatment Plant Re Exceedance in Bod ML18153B2161995-02-0101 February 1995 Advises That Plant Has Not Received Copy of Waste Shipment Record,Signed by Owner or Operator of Designated Waste Disposal Site within 45 Days Since Waste Shipped off-site ML20078H0711995-01-30030 January 1995 Discusses Conditions Affecting Safety of Project That Documents Problem Encounter W/Spillway EDG at Plant Main Dam & Informs on 950103 Spillway EDG Failed to auto-start During Performance of Monthly Periodic Test ML20078E1251995-01-25025 January 1995 Submits Notification Re Stationary Source Permit to Construct & Operate an EDG ML18153B2181995-01-23023 January 1995 Informs That Scientific Ecology Group,Inc Received Shipment S-94-14 Which Consists of 3 B-25 Boxes of Asbestos ML18153B2021995-01-0303 January 1995 Submits Follow Up to Telephone Notification Re Excursion of Total Suspended Solids Limitations at Plant Outfall 181 ML20080C1381994-11-30030 November 1994 Responds to Issues Identified in Repts for Technical & Lab Insps on 941018 & 20.Corrective Actions:Corrected DMR Forms Completed & Submitted to Dept of Environ Quality & TSS Worksheet Form Revised ML20077C2481994-11-22022 November 1994 Discusses Licensee Request for Relief from Ph Limitations in Plant Current Vpdes Permit at Outfalls 003 & 004 ML20078G8421994-11-0909 November 1994 Submits Response to Violations Noted in Insp Repts 50-338/94-10 & 50-339/94-10.Corrective Actions:Upset Conditions Corrected & Facility Performance Inproved ML18153B0611994-08-30030 August 1994 Requests 60-day Extension for Submittal of Initial Abatement Rept & SCR ML20071L6281994-07-28028 July 1994 Ack Receipt of Detailed Response to NPDES Insp Rept 1999-08-17
[Table view] |
Text
~I Westinghouse Energy Systems Box 355 Electric Corporation Pittsburgh Pennsylvania 15230-0355 July 25, 1994 VRA-94-079 Ref: 1) ET-NRC-92-3695
- 2) ET-NRC-92-3699 Mr. R. F. Saunders Vice President - Nuclear Operations Virginia Power Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, Virginia 23060 Virginia Power Surry Units 1 and 2, North Anna Units 1 and 2 Update on Containment and Accumulator Initial Temperature Assumptions for LB-LOCA Analysis
Dear Mr. Saunders:
References (1) and (2) previously provided the NRC with information concerning the effect on Large Break LOCA calculated Peak Cladding 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 the telecons and provide the current Westinghouse position on this issue.
To assist in the selection of the accumulator water temperature for Surry Units 1 & 2 and North Anna 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, C. M. Thompson (412-374-4409), or Ken Schrader (412-374-5069) if you have questions on this subject.
D.R. Beynon, Jr., Project Manager Virginia Area Domestic Customer Projects Attachment I
i 9400050037 940725 PDR ADDCK 05000280 ffJDI I I P PDR 0088GL-10
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Accumulator Water Temperature The 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 spacer grid model used in the BART and BASH versions of the Westinghouse 1981 Large Break 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, usjng the corrected versions of the Reference (6)
Evaluation model have shown a much smaller sensitivity to accumulator water temperature than reported 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°P. Since the sensitivity is now below the 10 CPR 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.
Accumulator Water Temperature Analysis Assumption All LOCA analysis performed to satisfy Appendix K to 10CPR50 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 noding, phenomena assumed in the calculation to predominate, including pump operation or locking, and values of parameters over their applicable ranges. For items to which results are shown to be 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 expected range have an effect which is not significant, where significant is currently defined as greater than 50°P. Application of this requirement to the choice of accumulator water temperature would result in a selection for which the effect of variations in water temperature during operation (@100% power) would not result in a significant change in the calculated PCT ( < 50°P).
If the accumulators are in a location where the water temperature would be expected to trend with containment air temperature, then an acceptable accumulator water temperature to use in Large Break LOCA analyses could be based on, 1) Tech-Spec maximum containment air temperature, 2) maximum fan cooler exhaust temperature, or 3) the estimated annualized average accumulator water temperature
(@ 100%_ power). Since the current sensitivity of PCT to accumulator water temperature is about 1.3 °P PCT for a 1 °F change in accumulator water temperature, the variation between the accumulator water temperature based on one of these definitions, and that used in the existing analysis should be less than 35°P (50°P/l.3°F PCT per 1 °P water temp). As an example, for the case of a plant with a Tech-Spec maximum air temperature of a 120°F and having a LOCA analysis which used 90°P as the minimum air temperature at 100% power, the range in- air temperature is less than 35°P. Thus an accumulator water temperature of 90°F or greater would be acceptable and could be justified in the analysis. If the location of the accumulators results in accumulator water temperatures which are either much hotter or colder than the containment 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.
- Since the effect of expecu9ariations in accumulator water temperatu,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.
Westighouse Recommendation on Accumulator Water Temperature Selection 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°P (50°P/1.3°P *pcT per 1°P water temp) then no immediate action is necessary. If the current assumption is more than 35 °P 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.
Refuelig Water Storage Tank CRWST} Temperature 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 to changes in RWST temperature. RWST temperature affects both the containment spray temperature. and pumped Safety Injection temperatures. RWST temperature assumptions of 40°P, 80°P and 120°P were investigated with the result that the maximum PCT occurred when the RWST was at 40°P and the sensitivity seen for increasing RWST temperature was *
-O.l6°P PCT/+ 1.0°P RWST. The ECCS model of Reference (6) uses the technical specification minimum RWST temperature for containment spray and the nominal RWST temperature for the pumped Safety Injection in the BASH reflood calculation, and this value can be set independently from the containment spray temperature used to calculate the containment pressure. This input methodology applied to analyses performed with the Reference (6) models, results in a slightly conservative PCT calculation by some 2 °P to 3 °P. This input method has been applied consistently 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 CPR 50.46 and Appendix K to 10 CPR 50 have historically used the minimum RWST temperature in the analysis as one of the features needed to satisfy Appendix K to 10 CPR 50, there is no need to change the current modeling and no need to modify current analysis calculated PCTs.
Containment Air Temperature Since the issuance of Reference (2) there has been no change in the Large Break LOCA PCT response to this parameter. Therefore, Westinghouse feels that the current modeling assumptions of using the minimum containment air temperature associated with 100% power is acceptable and will not change current practice.
CONCLUSION The 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 CPR 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. The sensitivity to RWST
temperature has been de.ned and found to have a negligible effectt!i calculated PCT. Therefore,
"" .. ~ WestiI1ghouse will forward fit the utility selected accumulator water temperature to new analyses
' performed with the models of Reference (5) or (6).
References
- 1. Letter ET-NRC-92-3695, N. J. Liparulo 00 to U. S. Nuclear Regulatory Commission, "10CFR21 Interim Report: LOCA Containment Initial Temperature Assumption", April 30, 1992.
- 2. Letter ET-NRC-92-3699, N. J. Liparulo 00 to U. S. Nuclear Regulatory Commission, "Results of Technical Evaluation of Containment Initial Temperature Assumptions for Large Break Loss of Coolant Accident Analysis", June 1, 1992.
- 3. Letter ET-NRC-92-3787, N. J. Liparulo 00 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. Liparulo 00, "Acceptance 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/Addenda (Non-Proprietary), Young, M.Y., "BART-Al: A Computer Code for the Best Estimate Analysis of Reflood Transients", March 1984.
- 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.
VRA-94-079 2 July 25, 1994 cc: M. L. Bowling C. B. Candee W L. M. Girvin E. W. Harrell M. R. Kansler M. L. Loftis J. P. O'Hanlon J. A. Price L. H. Roberts W J. A. Stall R. M. Berryman KL. Basehore D. A. Heacock S. R. Harms M. D. Crist D. M. Olson U.S. Nuclear Regulatory Commission ATfN: Document Control Desk Washington, DC 20555 Attention: Mr. F. Orr, Reactor Systems Branch Office of Nuclear Reactor Regulation 0088GL-11