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MONTHYEARML20246M0491989-05-10010 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, That Was Mutually Agreed Upon Between NRC & Westinghouse at 890411 Meeting.Util Schedule Not Approved Project stage: Meeting ML20059L6341990-09-20020 September 1990 Advises That No short-term Safety Concerns Noted Per 890530 Response to NRC Bulletin 88-011 Re Thermal Stratification Project stage: Other ML20091B2571991-05-17017 May 1991 Discusses LBB Analysis of Plant Unit 1 Pressurizer Surge Line Piping Which Allows Shims to Be Removed from Surge Line Pipe Whip Restraints.Lbb Analysis Was Approved,Therefore Surge Line Whip Restraint Shims Will Be Removed Project stage: Other 1990-09-20
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M1591999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217C6741999-10-0808 October 1999 Forwards RAI Re Licensee 970128 Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, . Response Requested within 60 Days of Receipt of Ltr ML20217E0301999-10-0707 October 1999 Forwards Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violation Noted Involving Failure to Correctly Translate Design Change Re Pertinent Operating Logs & Plant Equipment Labeling ML20212K8071999-09-30030 September 1999 Informs That on 990916,NRC Staff Completed mid-cycle Plant Performance Review (PPR) of Facility.Staff Conducted Reviews of All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility ML20216J9621999-09-30030 September 1999 Forwards Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Ncvs.One Violation Re Failure to Follow Operation Manual Procedure Associated with Configuration Control Identified ML20212M2661999-09-30030 September 1999 Forwards Order Approving Transfer of Licenses for Beaver Valley from Dlc to Pennsylvania Power Co & Approving Conforming Amends in Response to 990505 Application L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 ML20211Q3431999-09-0808 September 1999 Informs That During 990903 Telcon Between L Briggs & T Kuhar,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant,Unit 1.Insp Planned for Wk of 991115 ML20211Q5601999-09-0707 September 1999 Forwards Insp Rept 50-412/99-07 on 990720-29.Three Apparent Violations Noted & Being Considered for Escalated Ea. Violations Involve Failure to Implement C/As to Prevent bio- Fouling of Svc Water Sys L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 ML16342A8811999-08-23023 August 1999 Forwards Emergency Response Data Sys (ERDS) Implementation Documents for Listed Plants.Changes Should Be Made to ERDS as Soon as Possible.Without Encl 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info ML20211A5111999-08-18018 August 1999 Forwards Insp Repts 50-334/99-04 & 50-412/99-04 on 990613- 990724.One Violation Noted & Treated as Non-Cited Violation Involved Failure to Maintain Containment Equipment Hatch Closed During Fuel Movement L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes ML20209G5701999-07-12012 July 1999 Discusses Closure of TACs MA0525 & MA0526 Re Response to RAI Concerning GL 92-0,Rev 1,Suppl 1, Rv Structural Integrity. Info in Rvid Revised & Released as Ver 2 as Result of Review of Response ML20207H6621999-07-0808 July 1999 Forwards RAI Re Util 981112 Response to IPEEE Evaluations for Plant,Units 1 & 2.RAI Was Discussed During 990628 Telcon in Order to Ensure Clear Consistent Understanding by All Parties of Info Needed L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC ML20209D8191999-07-0707 July 1999 Forwards Insp Repts 50-334/99-03 & 50-412/99-03 on 990502- 0612.No Violations Noted.Program for Maintaining Occupational Exposures as Low as Reasonably Achievable (ALARA) & for Training Personnel,Generally Effective L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal ML20195H4651999-06-16016 June 1999 Forwards for Filing Answer of Firstenergy Corp in Opposition to Petition for Leave to Intervene of Local 29, Intl Brotherhood of Electrical Workers. Copies of Answer Have Been Served Upon Parties & Petitioner by e-mail ML20195J5221999-06-16016 June 1999 Forwards Answer of Duquesne Light Co to Petition to Intervene of Local 29,International Brotherhood of Electrical Workers in Listed Matter.With Certificate of Svc PY-CEI-NRR-2377, Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 11999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 L-99-100, Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-1091999-06-15015 June 1999 Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-109 L-99-095, Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys1999-06-15015 June 1999 Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys ML20207G8721999-06-0808 June 1999 Forwards Notice of Consideration of Approval of Transfer of Facility Operating Licenses & Issuance of Conforming Amends & Opportunity for Hearing.Application Seeks Approval of Proposed Transfer of Dl Ownership Interests in BVPS ML20207G2611999-06-0707 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195H3731999-06-0303 June 1999 Forwards Petition to Intervene of Local 29,Intl Brotherhood of Electrical Workers in Matter of Firstenergy Nuclear Operating Co,For Filing L-99-090, Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request1999-06-0202 June 1999 Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request L-99-089, Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)1999-05-28028 May 1999 Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b) L-99-086, Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 11999-05-28028 May 1999 Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 1 L-99-084, Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon1999-05-27027 May 1999 Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon IR 05000412/19980091999-05-26026 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-412/98-09 ML20195C4461999-05-21021 May 1999 Forwards Insp Repts 50-334/99-02 & 50-412/99-02 on 990321-0501.No Violations Were Identified.Licensee Conduct of Activities at Beaver Valley Power Station Characterized by Safe Conduct of Activities During Refueling Outage ML20206P1241999-05-14014 May 1999 Refers to Proposed Changes Submitted by Dl on 990316 to BVPS QA Program Described in BVPS-2 Ufsar,Chapter 17.2.Forwards RAI Re Proposed QA Program Changes L-99-071, Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS1999-05-12012 May 1999 Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062F2471990-11-16016 November 1990 Summarizes Staff Understanding of Current Status Re GSIs Remaining Unimplemented at Facility Based on Util 900627 Response to Generic Ltr 90-04 & 901025 Meeting ML20058D5321990-10-30030 October 1990 Forwards Addl Info Re Proposed Change Request 1A-176 Relating to Overpressure Protection Sys ML20058B6651990-10-19019 October 1990 Grants 901018 Request for Temporary Waiver of Compliance from Tech Spec 3.6.2.2 Re Reduced Flow Through Spray HXs ML20062B6621990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062A6961990-10-11011 October 1990 Responds to Util 900907 Request for Authorization to Use Alloy 690 for Steam Generator Tube Plugs.Use of Alloy 690 Acceptable ML20059N4651990-10-0101 October 1990 Forwards Insp Repts 50-334/90-19 & 50-412/90-19 on 900917- 21.One Noncited Violation Noted ML20059L6341990-09-20020 September 1990 Advises That No short-term Safety Concerns Noted Per 890530 Response to NRC Bulletin 88-011 Re Thermal Stratification ML20059E7531990-08-24024 August 1990 Forwards Requalification Program Evaluation Rept 50-334/90-14OL-RQ on 900709-19.Util Requalification Program Assigned Overall Rating of Satisfactory ML20058P3921990-08-10010 August 1990 Forwards Requalification Program Evaluation Rept 50-412/90-11(OL-RQ) Administered on 900529-0607.Program Assigned Overall Rating of Satisfactory ML20058N0711990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Establishment of Engineering Managers Forum ML20056A3511990-07-24024 July 1990 Forwards Safety Insp Repts 50-334/90-12 & 50-412/90-12 on 900505-0622 & Notice of Deviation ML20055G8071990-07-16016 July 1990 Forwards Insp Repts 50-334/90-15 & 50-412/90-15 on 900611-15.No Violations Noted ML20055G4251990-07-11011 July 1990 Forwards Radiological Controls Insp Repts 50-334/90-16 & 50-412/90-16 on 900604-08.No Violations Noted.Weaknesses Noted.Review of Weaknesses Requested & Results of Review Should Be Submitted to NRC by 900901 ML20058K4511990-06-29029 June 1990 Advises That NRC Has No Objection to Util Corrective Actions & Schedule for Unqualified Fire Damper Engineering Evaluations.Complete Review of Util Engineering Evaluations Will Be Issued Later ML20043H9141990-06-22022 June 1990 Advises That Financial Info for Participants Submitted for 1990 in Satisfies Requirements of 10CFR140.21 That Licensee Maintain Approved Guarantee of Payment of Deferred Premiums for Operating Reactor Over 100 Mw(E) ML20044A6041990-06-18018 June 1990 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 900801 in King of Prussia,Pa to Discuss Recent Format Changes to Requalification/Initial Exams. Proposed Agenda & Lodging Info Encl ML20059M9291990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20043F7961990-06-12012 June 1990 Requests That Util Inform Commission in Writing of Replacement of Independent Safety Evaluation Group ML20043G3191990-06-12012 June 1990 Forwards Safety Insp Rept 50-412/90-14 on 900430-0504.No Violations Noted ML20043F7361990-06-0808 June 1990 Grants 900606 Request for Temporary Waiver of Compliance from Requirements of Tech Spec 3.6.3.1 ML20034D0061990-05-25025 May 1990 Forwards Safety Insp Repts 50-334/90-11 & 50-412/90-10 on 900430-0504.No Violations Noted.Weaknesses Noted in Lab Qa/ QC Program.Complete Data from Independent Measures Taken Will Be Reported in Subsequent Insp Rept ML20043C0841990-05-24024 May 1990 Forwards Safety Insp Repts 50-334/90-10 & 50-412/90-09 on 900501-03.No Violations Noted ML20043C3171990-05-22022 May 1990 Advises That Assessing Intakes of Radioactive Matl Using Bioassay Data Should Be Based on Best Data & Models Available for That Purpose.Licensees May Use Improved & Generally Accepted Methodology Used in Icrp Publications ML20043B2951990-05-18018 May 1990 Forwards Safety Insp Repts 50-334/90-09 & 50-412/90-08 on 900331-0504.One Noncited Violation Identified Re Failure to Perform Required Surveillance Test ML20043A8391990-05-14014 May 1990 Advises That 891122 Request for Info Re Instrumented Insp Technique Test Results & Validity of Tests Performed by Hafa Intl,Inc Not Received.Response Requested within 20 Days of Ltr Date ML20043A2851990-05-10010 May 1990 Forwards Insp Repts 50-334/90-80 & 50-412/90-80 on 900226-0307.Weaknesses Identified.Overall Assessment of Program at Unit 2 for Development & Maint of symptom-based EOPs Found Very Good ML20042G3551990-05-0909 May 1990 Advises of Closeout of Generic Ltr 89-19, Actions Re Resolution of USI A-47, `Safety Implications of Control Sys in LWR Nuclear Power Plants ML20042G7831990-05-0404 May 1990 Informs of Proposed 900620-21 Workshop in King of Prussia,Pa to Promote Better Understanding of NRC Insp Program.Proposed Agenda Encl ML20042F4381990-05-0303 May 1990 Requests Submission of Westinghouse Reassessment of NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML20043A8961990-05-0202 May 1990 Forwards Agenda for NRC Region I Radiation Protection Managers Conference on 900523-24 in King of Prussia,Pa ML20042F3491990-04-27027 April 1990 Forwards Safety Insp Repts 50-334/90-07 & 50-412/90-06 on 900217-0330.No Violations Noted ML20034B7661990-04-19019 April 1990 Forwards Safety Insp Repts 50-334/90-08 & 50-412/90-07 on 900402-06.No Violations Noted ML20012C6781990-03-21021 March 1990 Reaffirms Granting of Temporary Waiver of Compliance W/Tech Spec 3.8.2.1, Onsite Power Distribution Sys & Informs of Plan to Issue Amend to Adopt Westinghouse STS Requirement Upon Expiration of Comment Period ML20012E6021990-03-19019 March 1990 Informs of 900523-24 Radiation Protection Manager Conference in King of Prussia,Pa to Discuss Issues of Mutual Interest Re Power Reactor Radiological Controls Program ML20012D3201990-03-16016 March 1990 Advises That Evaluation of Requalification Program & Licensed Personnel Scheduled for Wks of 900709 & 16.NRC Examiners Will Visit Site Approx 14 Days Prior to Evaluation.Ref Matls,Listed on Encl,Should Be Furnished ML20012D5661990-03-15015 March 1990 Forwards Safety Insp Repts 50-334/90-06 & 50-412/90-05 on 900226-0302.No Violations or Deviations Noted ML20012C3131990-03-13013 March 1990 Forwards Understanding of Current Status of All Unimplemented USIs for Plant,Per Generic Ltr 89-21 & Licensee 891127 Response ML20012D4641990-03-0909 March 1990 Forwards Safety Insp Repts 50-334/90-02 & 50-412/90-02 on 900101-0216.No Violations Noted ML20011F7071990-03-0101 March 1990 Forwards Request for Addl Info Re Util 890811 Second 10-yr Interval Insp Program Plan,Rev 1 & Associated Relief Requests.Response to Encl Questions Should Be Submitted within 45 Days of Ltr Receipt ML20033E3671990-02-27027 February 1990 Forwards Safety Insp Repts 50-334/90-03 & 50-412/90-03 on 900122-26.No Violations Noted.Corrective Actions Re Problems Experienced W/Aluminum Cables Require Further Mgt Attention & Will Be Reviewed During Future Insp ML20011F7431990-02-26026 February 1990 Forwards Insp Repts 50-334/89-80 & 50-412/89-80 on 890911-29.No Violations or Unresolved Items Noted.Response to Weakness Identified in Insp Rept Requested within 60 Days of Ltr Receipt ML20006F7711990-02-22022 February 1990 Advises That 900129 Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment, Acceptable ML20011F6771990-02-22022 February 1990 Advises That Evaluation of Requalification Program & Licensed Personnel Scheduled for Wks of 900528 & 0604.NRC Examiners Will Visit Site Approx 14 Days in Advance of Exams.Ref Matl,Listed on Encl,Should Be Furnished ML20006F3811990-02-16016 February 1990 Forwards Insp Rept 50-334/90-04 on 900122-26.Enforcement Conference Will Be Scheduled in Mar 1990 to Discuss Operation of 120-volt Ac Vital Instrument Bus in Degraded Condition W/O Restrictions NUREG-1057, Advises That Util May Decide to Revise Emergency Operating Procedure (EOP) Procedure Generation Package (PGP) Based on Safety Evaluation Submitted Via Unit 2 Sser 5 (NUREG-1057, Suppl 5) & Insps But Need Not Submit PGP Rev to NRC1990-02-16016 February 1990 Advises That Util May Decide to Revise Emergency Operating Procedure (EOP) Procedure Generation Package (PGP) Based on Safety Evaluation Submitted Via Unit 2 Sser 5 (NUREG-1057, Suppl 5) & Insps But Need Not Submit PGP Rev to NRC ML20033E0531990-02-15015 February 1990 Advises That 900130 Response to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations, Acceptable ML20006F3111990-02-15015 February 1990 Forwards Combined Safety Insp Repts 50-334/89-23 & 50-412/89-22 on 891118-1231 & Notice of Violation.Response Re Failure to Follow Written Procedures That Apparently Led to Unit 1 Safety Injection Actuation Requested ML20006F2681990-02-13013 February 1990 Forwards Final SALP Repts 50-334/88-99 & 50-412/88-99 for June 1988 - Aug 1989.Typos & Editorial Corrections Made After Review of Encl 900103 Response to SALP Rept.List of Meeting Attendees & 891124 Transmittal Ltr Also Encl ML20011E5911990-02-0707 February 1990 Forwards Safety Insp Repts 50-334/90-01 & 50-412/90-01 on 900108-12.No Violations Noted ML20011F0121990-02-0707 February 1990 Forwards Safety Insp Repts 50-334/89-25 & 50-412/89-23 on 891204-08 & Notice of Deviation 1990-09-20
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M1591999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217C6741999-10-0808 October 1999 Forwards RAI Re Licensee 970128 Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, . Response Requested within 60 Days of Receipt of Ltr ML20217E0301999-10-0707 October 1999 Forwards Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violation Noted Involving Failure to Correctly Translate Design Change Re Pertinent Operating Logs & Plant Equipment Labeling ML20212K8071999-09-30030 September 1999 Informs That on 990916,NRC Staff Completed mid-cycle Plant Performance Review (PPR) of Facility.Staff Conducted Reviews of All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility ML20216J9621999-09-30030 September 1999 Forwards Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Ncvs.One Violation Re Failure to Follow Operation Manual Procedure Associated with Configuration Control Identified ML20212M2661999-09-30030 September 1999 Forwards Order Approving Transfer of Licenses for Beaver Valley from Dlc to Pennsylvania Power Co & Approving Conforming Amends in Response to 990505 Application ML20211Q3431999-09-0808 September 1999 Informs That During 990903 Telcon Between L Briggs & T Kuhar,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant,Unit 1.Insp Planned for Wk of 991115 ML20211Q5601999-09-0707 September 1999 Forwards Insp Rept 50-412/99-07 on 990720-29.Three Apparent Violations Noted & Being Considered for Escalated Ea. Violations Involve Failure to Implement C/As to Prevent bio- Fouling of Svc Water Sys ML16342A8811999-08-23023 August 1999 Forwards Emergency Response Data Sys (ERDS) Implementation Documents for Listed Plants.Changes Should Be Made to ERDS as Soon as Possible.Without Encl ML20211A5111999-08-18018 August 1999 Forwards Insp Repts 50-334/99-04 & 50-412/99-04 on 990613- 990724.One Violation Noted & Treated as Non-Cited Violation Involved Failure to Maintain Containment Equipment Hatch Closed During Fuel Movement ML20209G5701999-07-12012 July 1999 Discusses Closure of TACs MA0525 & MA0526 Re Response to RAI Concerning GL 92-0,Rev 1,Suppl 1, Rv Structural Integrity. Info in Rvid Revised & Released as Ver 2 as Result of Review of Response ML20207H6621999-07-0808 July 1999 Forwards RAI Re Util 981112 Response to IPEEE Evaluations for Plant,Units 1 & 2.RAI Was Discussed During 990628 Telcon in Order to Ensure Clear Consistent Understanding by All Parties of Info Needed ML20209D8191999-07-0707 July 1999 Forwards Insp Repts 50-334/99-03 & 50-412/99-03 on 990502- 0612.No Violations Noted.Program for Maintaining Occupational Exposures as Low as Reasonably Achievable (ALARA) & for Training Personnel,Generally Effective ML20207G8721999-06-0808 June 1999 Forwards Notice of Consideration of Approval of Transfer of Facility Operating Licenses & Issuance of Conforming Amends & Opportunity for Hearing.Application Seeks Approval of Proposed Transfer of Dl Ownership Interests in BVPS ML20207G2611999-06-0707 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart IR 05000412/19980091999-05-26026 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-412/98-09 ML20195C4461999-05-21021 May 1999 Forwards Insp Repts 50-334/99-02 & 50-412/99-02 on 990321-0501.No Violations Were Identified.Licensee Conduct of Activities at Beaver Valley Power Station Characterized by Safe Conduct of Activities During Refueling Outage ML20206P1241999-05-14014 May 1999 Refers to Proposed Changes Submitted by Dl on 990316 to BVPS QA Program Described in BVPS-2 Ufsar,Chapter 17.2.Forwards RAI Re Proposed QA Program Changes ML20206N3161999-05-0606 May 1999 Responds to Ltr to NRC on Continued Events Re Transfer of Generation Assets Between Dl & Firstenergy.Info Will Be Considered as NRC Monitor Pending License Transfer Application of Bvps,Units 1 & 2 & PNPP ML20206H7931999-04-30030 April 1999 Ack Receipt of 990426 Request for Enforcement Discretion & 990427 Withdrawal of Request for Enforcement Discretion. Resolution Documented.Enforcement Discretion Not Necessary ML20206B2751999-04-22022 April 1999 Forwards Insp Repts 50-334/99-01 & 50-412/99-01 on 990207- 0320.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206A8381999-04-20020 April 1999 Forwards Reactor Operator Initial Exam Rept 50-412/99-301 on 990322-25.All Three Reactor Operator Applicants Passed. Initial Written Exam Submittal Was Determined Not to Meet NRC Guidelines in Certain Instances ML20205R9071999-04-20020 April 1999 Forwards Second Request for Addl Info Re Response to GL 95-07, Pressure-Locking & Thermal-Binding of Safety-Related Power-Operated Gate Valves, for Beaver Valley Power Station,Units 1 & 2 IR 05000334/19980111999-04-14014 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-334/98-11 & 50-412/98-11 Issued on 990225.Actions Will Be Examined During Future Insp of Licensed Program ML20205P2431999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Ltr Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival ML20205L0341999-04-0909 April 1999 Forwards SER Accepting Util 971209 & 980729 Submittal of Second 10-year Interval ISI Program Plan & Associated Relief Requests for Beaver Valley Power Station,Unit 2.TER Also Encl ML20205K0901999-04-0505 April 1999 Informs of Individual Exam Result on Initial Retake Exam Conducted on 990322-25 at Licensee Facility.Three Individuals Were Administered Exam & All Three Passed. Forwards Encl Re Exam.Without Encl ML20205R1791999-03-30030 March 1999 Responds to Issue Re Generic Implication of part-length Control Rod Drive Mechanism Housing Leak at Praire Island, Unit 2 & Beaver Valley Power Station,Units 1 & 2 ML20205C0301999-03-26026 March 1999 Informs That Util Responses to GL 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling & Containment Heat Removal Pumps Acceptable ML20204D7371999-03-16016 March 1999 Advises That RW Lindsey Authorized to Administer Initial Written Exams to Sh Cencic,Tf Lardin & Ta Pittas on 990322. Region I Operator Licensing Staff Will Administer Operating Tests ML20207E0201999-02-25025 February 1999 Forwards Insp Repts 50-334/98-11 & 50-412/98-11 on 981227- 990206 & Forwards Notice of Violations Re Uncontrolled Reduction of Main Condenser Vacuum ML20203D0691999-02-10010 February 1999 Forwards SE Accepting Approval of Proposed Revs to Plant QA Program Description in Chapter 17.2 of Updated Fsar,Per Util 981224 Submittal ML20206U3011999-02-0505 February 1999 Forwards Insp Repts 50-334/98-09 & 50-412/98-09 on 981116-1217 & Nov.Violation Identified Re Inadequate Design Control in Unit 2 Dc Voltage Drop Calculation ML20203A0811999-02-0404 February 1999 Forwards Request for Addl Info Re Review of Beaver Valley Power Station,Unit 1 License Amend to Allow one-time Extension of Steam Generator Insp Interval ML20199E6681999-01-14014 January 1999 Forwards RAI Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Plant,Units 1 & 2 ML20199F1961999-01-13013 January 1999 Forwards Insp Repts 50-334/98-10 & 50-412/98-10 on 981115-1226.No Violations Noted.Informs That Overall Fire Protection Program Functioning Well ML20199F5101998-12-29029 December 1998 Discusses Third 10-year Interval ISI Program Plan & Associated Relief Requests for BVPS-1 Submitted by Dlc on 970917 & 980618.Informs That NRC Has Adopted Ineel Recommendations in TER INEEL-98-00893.Forwards SE & TER ML20198K5911998-12-24024 December 1998 Forwards Emergency Response Data Sys Implementation Documents Which Include Data Point Library Updates for Fermi (Number 268),Peach Bottom (Number 269) & Beaver Valley (Number 270).Without Encls ML20198K8251998-12-21021 December 1998 Forwards SER Granting Licensee 980611,as Suppl 981015 Pump Relief Request PRR-5 for Third 10-year IST Interval for Beaver Valley Power Station,Unit 1 Pursuant 10CFR50.55(a)(f)(6)(i) ML20198A1301998-12-0909 December 1998 Forwards SE Re USI A-46 Program Implentation for Plant Unit 1.Staff Concludes Program Implementation Met Purpose & Intent of Criteria in Generic Implementation Procedure 2 & Suppl SER 2 for Resolution of USI A-46 ML20198B1301998-12-0909 December 1998 Advises of Planned Insp Effort Resulting from Beaver Valley Power Station mid-year Insp Resource Planning Meeting Held on 981110.Historical Listing of Plant Issues & Details of Insp Plan for Next 6 Months Encl ML20196J2761998-12-0404 December 1998 Forwards Corrected Pages 17 & 18 of NRC Integrated Insp Repts 50-334/98-06 & 50-412/98-06 for Exercise of Enforcement Discretion ML20196H3051998-12-0202 December 1998 Forwards Insp Repts 50-334/98-06 & 50-412/98-06 on 981004-1114.No Violations Noted.Conduct of Activities at Beaver Valley Power Station Facilities Characterized by Safe Plant Operations ML20196H2781998-12-0202 December 1998 Forwards Insp Repts 50-334/98-08 & 50-412/98-08 on 981026- 30.No Violations Noted.Plant Operations Witnessed by Team Were Conducted in Safe & Controlled Manner ML20196G9921998-12-0101 December 1998 Forwards Ltrs from Fk Koob, to JW Pack & CF Wynne Re Plant Deficiencies Assessed During 981006 Exercise Against Hancock County,Wv & Beaver County,Pa,Respectively ML20196D4371998-11-25025 November 1998 Discusses Concerns Re Announced Asset Transfer Between Firstenergy Corp & Duquesne Light Co ML20196A7101998-11-24024 November 1998 Forwards Notice of Withdrawal of Amend to License NPF-73. Proposed Change Would Have Extended on one-time Only Basis, Surveillance Interval for TSs 4.8.1.1.1.b & 4.8.1.2 Until First Entry Into Mode 4 Following Seventh Refueling Outage ML20195K3331998-11-18018 November 1998 Informs That Effective 981214,DS Collins Will Become Project Manager for Beaver Valley Power Station,Units 1 & 2 IR 05000334/19980041998-11-13013 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-334/98-04 & 50-412/98-04 Issued on 980915.C/As Will Be Examined During Future Insp of Licensed Program ML20195J2941998-11-12012 November 1998 Forwards Safety Evaluation Re First & Second 10-year Interval Inservice Insp Request for Relief 1999-09-08
[Table view] |
Text
b, September 20, 1990 bocket,No.50-334 S,erial No. BV-90-010 Mr. J. D. Sieber, Vice President Nuclear Group Duquesne Light Company P. O. Box 4 Shippingport, Pennsylvania 15007
Dear Mr. Sieber:
SUBJECT:
BULLETIN 88 PRES 7URIZER SURGE LINE THERMAL STRATIFICATION:
EVALUATION OF WESTINGHOUSE OWNERS GROUP BOUNDING ANALYSIS (TAC 72110)
Duquesne Light Company responded to Item 1.b of NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification, by letter dated May 30, 1989.
That response provided a Justification for Continued Operation (JCO) which referenced Westinghouse iopical Report WCAP 12277 (which was submitted separately by the Westinghouse Owners Group (WOG)).
The JC0 concluded that it would be acceptable for Beaver Valley, Unit 1 to continue power operation for at least several years even though thermal stratification in the surge line introduces thermal transients not considered in the design.
The JC0 and the Topical Report together form the bounding analysis to meet the intent of Item 1.b of Bulletin 88-11.
The staff has completed its review of the WOG bounding analysis and has con-cluded that there are no short-term safety concerns associated with thermal stratification effects for the duration of 10 additional heatup/cooldown cycles of continued operation.
The staff's Safety Evaluation supporting this conclusion is enclosed A copy of the evaluation also has been sent to the WOG.
The staff will assess the conformance of the pressurizer surge line to applicable codes and regulatory requirements for the 40 yev plant life when the WOG report regarding item i.d of the bulletin is submitted.
Sincerely, original signed by Albert De Agazio Albert W. De Agazio, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page
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September 20, 1990 Docket No. 50-334 Serial No. BV-90-010 4
Mr. J. D. Sieber, Vice President Nuclear Group Duquesne Light Company P. O. Box 4 Shippingport, Pennsylvania 15007
Dear Mr. Sieber:
SUBJECT:
BULLETIN 88 PRESSURIZER SURGE LINE THERMAL STRATIFICATION:
EVALUATION OF WESTINGHOUSE OWNERS GROUP BOUNDING ANALYSIS (TAC 72110)
Duquesne Light Company responded to Item 1.b of NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification, by letter dated May 30, 1989.
That response provided a Justification for Continued Operation (JCO) which referenced Westinghouse Topical Report WCAP 12277 (which was submitted separately by the Westinghouse Owners Group (WOG)).
The JC0 concluded that it would be acceptable for Beaver Valley, Unit I to continue power operation for at least several years even though thermal stratification in the surge line introduces thermal transients not considered in the design.
The JC0 and the Topical Report together form the bounding analysis to meet the intent of ltem 1.b of Bulletin 88-11.
The staff has completed its review of the WOG bounding analysis and has con-cluded that there are no short-term safety concerns associated with thermal stratification effects for the duration of 10 additional heatup/cooldown cycles of continued operation.
The staff's safety Evaluation supporting this conclusion is enclosed A copy of the evaluation also has been sent to the WOG.
The staff will assess the conformance of the pressurizer surge line to applicable esdes and regulatory requirements for the 40 year plant life when the WOG report regarding item 1.d of the bulletin is submitted.
Sincerely, Albert V. De Agazio, Sr.Pr ject Manager Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page l
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Mr. J. Sieber Beaver Valley-Power Station Duquesne Light Compoay Units 1 & 2 cc:
Jay E. Silberg, Esquire Bureau of Radiation Protection-Shaw, Pittman, Potts and Trowbridge Pennsylvania Department of 2300 N Street N.W.
Environmental Resources Washington, DC 20037 ATTN:
R. Janati Post Office Box 2063 Nelson Tonet, Manager Harrisburg, Pennsylvania 17120 Nuclear Safety Duquesne Light Company Mayor of the Borrough of P. O. Box 4 Shippingport Shippingport, Pennsylvania 15077 Post Office Box 3 Shippingport, Pennsylvania 15077 Commissioner Roy M. Smith Regional Administrator, Region I k
West Virginia Department of Labor U.S. Nuclear Regulatory Commission Building 3, Room 319 475 Allendale Road Capitol Complex King of Prussia, Pennsylvania 19406 Charleston, WV 25305 John D. Borrows Resident Inspector Director, Utilities Department U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 181 180 East Broad Street Shippingport, Pennsylvania 15077 Calumbus, Ohio 43266-0573 Director, Pennsylvania Emergency Management Agency Post Office Box 3321 Harrisburg, Pennsylvania 17105-3321 S
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Page 1 of 8 d
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NRR REVIEW 0F WESTINGHOUSE OWNERS GROUP (WOG)
BOUNDING EVALUATION FOR PRESSURIZER SuaGE LINE j
D THERMAL STRATIFICATION t
D WCAP-12277 INTRODUCTION The pressurizer surge line (PSL) in the pressurized water reactors (PWRs)..
?
is a stainless steel pipes connecting the bottom of the pressurizer vessel 1
b to the hot leg of the coolant loop.
The out flow of the pressurizer water is generally warmer than the. hot-leg flow.
Such temperature differential s
h (c?) varies with plant operation activities and can be as high as 320*F i
during the-initial-plant heat ep.
Thermal stratification.is the separation of cold flow stream in the horizontal portion of the PSL resulting in temperature difference at the top and bottom of the pipe.
Since thermal stratification is the direct result of-the differences in j
1 densities between the pressurizer water and the hotfleg' water, the l
potential for stratification is increased as system AT increasesland as-the insurge or outsurge flow decreases.
Stratification in PSL was found 1
recently and confirmed by data measured from several PWR plants.
Original design analyses did not include any stratified flow loading.
l conditions.
Instead it assumed complete sweep of fluid along the line during insurges or outsurges--resulting in uniform thermal loading at any particular piping locstion. Such analyses did not reflect PSL actual thermal condition and potentially may overlook undesirable line deflection -
and its actual high stresses may exceed design limits.
In addition, the 1
striping phenomenon, which'is the oscillation of the hoc and cold i
stratified boundary, may inducs.high cycle fatigue a the inner pipe wall and needs also to be analyzed. Thus assessment of stratification effects-i on PSL is necessary to ensure piping integrity and ASME Code Section III-conformance.
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Page 2 of 8 STAFF EVALOATION Since stratification in PSL is a gev rit concere to all PWRs an NRC Information Notice No 88-80 was itwN co Mtobv 1,1988, and then an NRC i
Bulletin 88-11 for the same concern m Osu issued on December 20, 1988..
Westinghouse, on behalf of the Westir.gh e n N ners Group (WOG), has performed a generic boundbg evaluativ m; ort WCAP-12277 (Reference 1).
This report provides the technical bas!. for tre generic justification for continued operation (JCO), for each of the WOG plants and constitutes compliance with the requested action 1.b of bulletin 88-11.1 Plants which.
heve discovered any gross discernable distress dering performance of the.
walkdown, as requested by Bulletin's action 1.a. should report findings i
and specify corrective actions in their JCO, in addition to. that provided in this report.
_The following is the staff's evaluation of the Westing-house's efforts and information provided in the report.
Prior to the issuance of the Bulletin, WOG implemented a program to address the issue of the surge line thermal stratification. The-program consisted of plant-specific analysis covering five plants and a review of l
thermal monitoring data from eight plants.
Westinghouse had instrumented PSLs and collected data for verifying stratification conditions. Tim thermal monitoring data obtained considered outside wall temperatures at different location around the pipe and along the axis of the pipe vs.
i L
time, vertical and lateral displacements at various locations along the pipe vs. time, and various plant parameters vs. time, from existing plant instrumentation and control sensors.
In some cases the data were based l
not only on plant heatup but also on. operation and plant cooldown l
conditions. The specific analyses included redefinition of revised p'
thermal transients considering stratification effects and evaluation of pipe stress and fatigue usage factors.
The overall analytical approach used in all these cases have been consistent and has been reviewed in detail by the NRC staff.
The evaluation concluded that a single bounding analysis was not= feasible.
j-Due to the variations in design, Westinghouse could not define a single -
E envelope case to justify the 40 year life of the surge line, therefore a bounding evaluation was performed to justify continued operation for at least ten (10) additional heatup/cooldown cycles..
The, bounding evaluation is essentially a demonstration of the applicability of the plant-specific and the moMtoring results to the remaining WOG plants All plant-specific analyses completed to-date, have demonstrated l
s 40 year life of the surge line l
j; Two-sets of parameters were defined.
.a)
Parameters which affect severity of thermal stratifica-o tion (i.e thermal hydraulic and operational effects)
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b)
Parameters which affect PSL response to thermal strati-
. fication (i.e. structural effects).
The range of the parameters-for.the plants analyzed and/or monitored was used to establish the bounding criteria and to enable an individual plant by plant comparison.
7 To expand the data base for a wider range of PSL configurations, Westinghouse recommended additional plant monitoring based on plant j
similarities (grouping), and surge line physical, design and operational parameters of all 55 domestic Westinghouse plants.
Plants with parameters not within the range of the current monitoring database were recossended for additional monitoring. Ten (10) different groups were identified for the 55 domestic. Westinghouse plants for data collection, review and analysis of the pertinent: thermal hydraulic, ooerational and structural-parameters.
Currently. 22 separate menitoring programs are either completed, in process, or being planned.
About 40% of the plants falling in one group with the remaining 60% of the Westinghouse PWR's divided among the I
nine groups. When this program is completed, it will provide sufficient monitoring data with at least one pient monitored in each group.
Parameters which have a significant effect from a thermal hydraulic stand point are pipe inside diameter and slope. Plants falling outside the resulting bounding criteria of pipe inside diameter of 7" to 15.4" and pipe average slope of 0* to 1.44' degrees, were recommended for monitoring.
The range of the parameters was expanded by 1 20% in determining a bounding criteria to which other plants were compared.
It was concluded that a bounding evaluation which is based on enveloping techniques, will not have a significant-effect on the thermohydraulic behavior due to a i 20% change in pipe size and slope.
The staff: agrees with Westinghouse's efforts and methodology for monitoring, updating and assessing PSL for the 3
stratification condition.
Thermal hydraulic evaluations using higher slope and smaller diameter pipe are expected to reduce the stratification effects.
Eleven plants have an average slope higher and one plant has a pipe size smaller than that
' j allowed by the criteria.
Some parameters judged to be relatively significant for the structural I
effects are:
Entra6ce angle to the hot leg nozzle Mid line riser 1
Length of the longest straight run of pipe Type of in-line component Presence of whip restraints Number of vertical rigid supports I
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Page 4 of 8 s
Y Two plants-have longest straight run lengths which are less than the -
t minimum in the criteria, and four plants have welded lugs or trunnion V
attachments to PSL.
Since none of the analysis to date has. included evaluation of welded attachments, which may increase thermal stresses due to structural discontinuities, this condition falls outside the criteria and the following has been recommended, a)
Inspection of these welds during walkdown b)
Evaluation of these attachments on a. plant-specific basis.
L The five plant specific analysis consisted of three parts: (1) global i
effects on stresses, moments, displacements, and support reaction loads, e
based on both axial and radial variations in the pipe metal temperature, (2) local stresses due to thermal gradient, and (3) local stresses and effects to fatigue due to thermal striping.
The global and loca1' stresses.
j L
in items (1) and (2) above wer= :9perimposed to obtain total stresses. -In l,
addition to the detailed plant speciffa analysis fra the five plants, twelve (12) plants-have completed interim
- valuations of the surge line L
stratification which include Finite Element structural analysis of each-L specific configuration under stratified conditlons.
The five plants for which detailed plant-specific analyses performed and evaluation reports submitted to NRC,'are as follows:
Seabrook (see WCAP-12151 and Suppl. 1, and WCAP-12305) South Texas Units 1-and 2 (see WCAP-12067 Rev 1 and Suppl. 1) Vogle Unit 2 (see WCAP-12132, WCAP-12199 and WCAP-12218) Beaver Valley Unit 2 (see WCAP-12093 and Supp1's 1 and 2) Comanche Peak Unit 1 (see WCAP-12248 and Suppl. 1)
Based on these reviews Westinghous concluded that a shorter horizontal' length will result in lower loads since the the surge line will experience 1ess vertical deflection and it will tend __to to-result in a'more uniform 1
di Gribution of the bending moment due to stratified loading..Ii1 addition middle line risers will also tend to-reduce the stratification effects.
The stratification induced global bending of the surge line:was calculated d
1 L'
using ANSYS computer code.
Although a 320*F step temperature change was
)
assumed for stratification through out the surge line, the changes were linearized in ANSYS using conventional pipe element model.
Finite Element i
models were used to calculate local stresses due to top-tobottom non-linear i
thermal gradients in the PSL.
Five (5) hot-to-cold interface locations were analyzed using eleven (11) cases of-thermal stratification, to calculate piping response under all required loading conditions, reflecting c-temperatures differences up to 320*F.
Other cases were obtained by g
interpolation.
Westinghouse reported that their best estimate analytical results compared favorably with measured displacements data observed l
during monitoring.
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Page 5 of 8 In two of the analyses, a rigid vertical support was removed. In one case it was shown that the support was not required, and in the other case it was replaced with a snubber and a spring.
The PSL was subsequent 13 re qualified and found acceptable.
Stress summary results from the five plant-specific analyses performed te, date indicates that the primary plus secondary stress intensity range ratio of equation 12 of ASME III section N8-3600, 1s-less than 1.0.
The M
critical location for stress is usually the safe end weld of the nozzle connecting the surge line to the primary loop hot leg.
In one case only
't it was determined to be at the reducer.
This seem to be a unique case since no_ other utility within the WOG has a mid line reducer in the PSL.
i Stresses were intensified by "K" factors, to account for the~ worst case concentration for all piping elements in the PSL The staff agrees-with the approaches used by the licensee for perform'.,, PSL reanalysis, To account for the thermal striping effects to PSL, q
v sodel test results, performed for the Liquid Metal Fast Breeder kew r primary loop and for the Mitsubishi Heavy Industries Feedwater Line cratm ing, were reviewed to establish the boundary condition.
These' test revults were used to define striping oscillation data, amplitude and frequencies, for evaluating high cycle fatigue.
Portions of PSL which experience stratification and striping were defined based on measured results.
Westinghouse reported that considering AT attenuation with time, and a-frequency of.30 HZ, a usage-factor of less'than.20 was' determined as the worst case dre to striping alone, even when the stresses were intensified
-by "K" factors.
The worst case element was determined to be the-butt weld.
A surface ~ film coefficient of 500 BTU /hr-sq. ft- *F was used and it was based on'a flow rate of 90 gpm,which was-assumed to be constant.
L throughout all striping analysis.
Although'the data used in the assess-ment weee obtained from scale test model which showed-that the frequency can range from.10-10 HZ. the staff agreed that the stresses will be higher with the lower frequency and'the.30 HZ.naverage frequency is J
justified.
However the thermal striping potential due to a film coef ficient of 500 BTU /hr-sq. ft.
'F and attenuation of AT is.
-1 questionable, but at this time no other better number exists and therefore this represents the best judgement.
If other information will be available, based on~ the ongoing efforts by EPRI or possible future NRC research work, it will be utilized and further assessments will be made for assessing the i
striping effects to PSL.
/
With-the thermal transients redefined, new fatigue usage factors were i
calculated.
To determine the new fatigue usage factors, the more detail j
. techniques-of ASME'III NB-3200 were employed.
Due to the non-axisymmetric-1 nature of stratification loading, stressac due to all loadings were-obtained from Finite Element analysis and then combined on a stress compo-nent basis.
Five (5) levels of thermal stratification at five worst case e
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Page 6 of 8 j
points were calculated using the WECEVAL program.
Stresses were intensified
?
c by "K" factors to account for worst case concentration in the piping elements.
Westinghouse reported that a cumulative usage factor (CUF)~of 0.73 was -
determined to be the worst case at the hot leg nozzle safe end location for all but one case.
l
. tine and the CUF at that location was determined to 0.94.For that case a op The CUF included Jf
' contributions from both global bending and local effects of stratifi--
gli d
cation considering the nonlinear step change top to bottom temperature distribution and striping.
Stresses resulting from primary. loading such as pressure, dead weight, and seismic are not affected by thermal stratification loading and typically 1
have a minor effect on the calculation of the fatigue usage factor.
c The contribution of seismic loadings to the cumulative usage factor from the W
plant specific analyses was reported to be 18%.
s All of the detailed plant l
specific analyses assumed the occurrence of twenty cperational earthquakes.-
r The staff agrees with the approaches used by Westinghouse for calculating b
the usage factor.
1 l'
Westinghouse reported that the PSL fatigue life is primarily depended upon s
1;-
the number of heatup and cooldown cycles.rather than the years of operation.
[
The worst case years of operation.at-any WOG plant is 28.5 years. 'The worst case number of heatup cooldown cycles is 75 and occurs at a different-plant.
Based on the combination of.these two worst case values an i
" Operating Life Factor" (OLF) of 0 44 is obtained which indicates that no l-more than 50% of the operating life has.been used at any Westinghouse L
plant to date.
For the generic case of a CUF = 1.0 a 17% value was attributed to age and an 83% was attributed to fatigue with a 20% of the L
83% value attributed to striping.
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Page 7 of 8i CONCLUS10NS' A
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Based on our review, we conclude that the information provided by
. Westinghouse in references 1 and 2, is comprehensive and acceptable.
Westinghouse on behalf of the Owners Group had made acceptable efforts to
. provide technical basis for the licensee's JC0 as indicated in'the requested ~ actions of the NRC Bulletin 88-11, item 1.b.
The staff.
believes that there is no immediate or short ters safety concerns associated with the stratification effects for 10 additional heatup/.
couldown cycles of continued plant operation.
However, each of the h0Gl l!
plants should submit a JC0 using this report as the basis.
We will assess:
if the surge line in each plant meet the code acceptance criteria for the 40 year plant life when additional generic analyses based on plant grouping is performed by Westinghouse for the Owners group.
l PRINCIPAL CONTRIBUTORS:
S. Hou l
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REFERENCES 1.
Westinghouse-Report WCAP-12T77 (Proprietary), and WCAP-12278 (Non-Proprietary).
" Westinghouse Owners Group bounding evaluation for Pressurizer surge Line thermal stratification,"' June ~ 15,1988.
i 2.
Viewgraphs by Westinghouse.
Presentation to NRC on May 23 and 24.
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