Letter Sequence Supplement |
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MONTHYEARML20128H1261985-06-0606 June 1985
Summary of 831219 Meeting W/Util & S&W in Bethesda,Md Re Util Equipment Qualification Program.Meeting Agenda & Supporting Documentation Encl
Project stage: Meeting
ML20205Q1051986-05-23023 May 1986
Forwards Vols 1-1C to Equipment Qualification Rept - Environ Qualification of Class 1E Electrical Equipment. Representative Sample of Equipment Will Be Installed & Available for Insp in Support of NRC Audit
Project stage: Other
ML20206E6191986-06-16016 June 1986
Notification of 860701 Meeting W/Util in Bethesda,Md to Discuss Technical Issues Re Util 860523 Equipment Qualification Rept,Identified as SER Confirmatory Issue 14, in Preparation for NRC Audit
Project stage: Meeting
ML20203G4881986-07-28028 July 1986
Summary of 860701 Meeting W/Util,Westinghouse & S&W in Bethesda,Md Re Preparation for Onsite Equipment Qualification Audit.Agenda & Attendee List Encl.Audit Expected to Take Place in Aug 1986
Project stage: Meeting
ML20205C3281986-08-0404 August 1986
Forwards Addendum 1 to 2BVM-166, Sqrt & Pump & Valve Operability Review Team (Pvort) Audit Program & Updated Master Equipment List,Per Sqrt/Pvort 860723 Premeeting.List Submitted to Support NRC 860930 Audit
Project stage: Meeting
ML20210F6021986-09-20020 September 1986
Forwards Rev 1 to Vols 1,1A,1B & 1C to Equipment Qualification Rept - Environ Qualification of Class 1E Electrical Equipment. Review & Schedule of NRC Audit Requested.List of Specs & Status of Util Response Also Encl
Project stage: Other
ML20215N2011986-10-23023 October 1986
Discusses Results of 860701 Meeting W/Util & Contractor in Preparation for Equipment Qualification Onsite Review.Onsite Review Scheduled for 861117-21.Access for Review Team Members Requested
Project stage: Meeting
ML20214E5881986-11-19019 November 1986
Notification of 861120 Meeting W/Util in Shippingport,Pa to Discuss Applicant Personnel Findings Made During Equipment Qualification Site Audit
Project stage: Meeting
ML20214V9041986-12-0303 December 1986
Forwards Updated Environ Qualification Program for Safety- Related Mechanical Equipment in Response to FSAR Questions 270.2 & 270.3 Identified in FSAR Amend 4.Qualification Methodology & Results Discussed
Project stage: Other
ML20207D4731986-12-19019 December 1986
Forwards Supplemental Info Re Evaluation of Superheated Steam Blowdown on Environ Qualification of Facility Equipment,Per 861125 Telcon.Response Provides Addl Info on Computer Codes Utilized in Superheat Evaluation
Project stage: Supplement
ML20212J5431987-03-0404 March 1987
Forwards Response to Specific & Generic Comments from Nrc/ NRR Environ Qualification Audit on 861118-20.Info Indicates That Action to Address Specific Comments Completed & Action to Address Generic Comments Prior to Fuel Load Underway
Project stage: Other
ML20207R0571987-03-0505 March 1987
Forwards Comments for Resolution Re SER Confirmatory Issue 14 Identified During Equipment Qaulification Review Team 861118-20 Audit.Response Requested within 45 Days of Ltr Receipt
Project stage: Other
ML20205G3791987-03-24024 March 1987
Forwards Responses to NRC Requests for Info Re Environ Qualification Program,Including High Energy Line Break W/ Superheat & Qualification Methodology for Submergence
Project stage: Other
ML20205F9351987-03-26026 March 1987
Forwards Environ Qualification of Safety-Related Mechanical Equipment, Including Rev 1 to Books 1-3 Re Masonelian air-operated Valves,Rev 4 Re Xomox Plug Valves & Rev 5 Re Pacific Charging Pumps,Per P Tam 870317 Telecopy
Project stage: Other
ML20214J6701987-05-18018 May 1987
Notifies of Completion of Environ Qualification (EQ) Effort for Facility EQ Packages in Compliance w/10CFR50.49. Potential 10CFR50.55(e) Items Re Improper Sealing of EQ Program Equipment Will Be Submitted within 30 Days
Project stage: Other
ML20214J4911987-05-25025 May 1987
Interim Significant Deficiency Repts 87-16 & 87-17 Re Conduit Sealing of 50 Class 1E Items.All Physical Work Re Re Environ Qualification Program Complete W/Exception of Four Bisco Seals
Project stage: Other
1986-07-28
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Category:CORRESPONDENCE-LETTERS
MONTHYEARIR 05000412/19990071999-10-21021 October 1999
Refers to Special Team Insp 50-412/99-07 Conducted from 990720-29 & Forwards Nov.Two Violations Identified.First Violation Involved Failure to Implement C/A to Prevent Biofouling of Service Water System
ML20217M1591999-10-19019 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
L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999
Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct
L-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999
Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections
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
L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999
Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program
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
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
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
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
L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999
Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC
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-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999
Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)
L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999
Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls
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-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999
Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3
L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999
Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl
L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999
Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B
L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999
Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change
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
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-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999
Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001
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-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999
Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by
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
L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999
Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl
L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999
Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6
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
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-99-108, 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
L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl
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
L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999
Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999
Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections
L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999
Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct
L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999
Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program
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
L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999
Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC
L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999
Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)
L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999
Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls
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-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999
Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3
L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999
Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl
L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999
Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change
L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999
Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B
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
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
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-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999
Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001
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
L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999
Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by
L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999
Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl
L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999
Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6
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
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-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl
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
L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999
Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages
ML20196A6601999-06-16016 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
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
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
L-99-099, Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr1999-06-14014 June 1999
Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr
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-99-086, 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-99-089, 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-99-084, 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
L-99-082, Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS1999-05-17017 May 1999
Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS
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
1999-09-03
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059L4271990-09-0707 September 1990
Requests Approval for Use of Steam Generator Tube Plugs for Both Mechanical & Welded Applications
ML20059G0821990-09-0404 September 1990
Forwards Application for Amend to License DPR-66,consisting of License Change Request 180,changing Section 3.3.3.2 to Reduce Required Number of Operable Incore Detector Thimbles for Remainder of Cycle 8
ML20059F7551990-08-29029 August 1990
Responds to Unresolved Item 50-334/90-16-01 Noted in Insp Rept 50-334/90-16.Corrective Actions:Initial Training for Maint Group Personnel Responsible for Maintaining Supplied Air Respirators Will Be Supplemented W/Biennial Retraining
ML20059F1501990-08-29029 August 1990
Advises That Permanent Replacement Chosen for Plant Independent Safety Evaluation Group.Position Will Be Staffed Effective 900829
ML20028G8731990-08-29029 August 1990
Forwards fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.71
ML20059D3761990-08-24024 August 1990
Describes Cycle 3 Reload Design,Documents Util Review Per 10CFR50.59 & Provides Determination That No Tech Spec Changes or Unreviewed Safety Questions Involved.Reload Core Design Will Not Adversely Affect Safety of Plant
ML20028G8881990-08-24024 August 1990
Withdraws Operator License SOP-10731 (55-60749) Issued to K Gilbert,Who Resigned
05000412/LER-1990-007, Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued1990-08-23023 August 1990
Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued
ML20058P7651990-08-14014 August 1990
Provides Info on Acceptability of Rescheduling Response to Reg Guide 1.97 Ser,Item 4b, Neutron Flux Monitoring Instrumentation. Rescheduling of Util Response Will Be Determined on or Shortly After Meeting W/Nrc
ML20059E0571990-08-10010 August 1990
Forwards Suppl 3 to Nonproprietary WCAP-12094 & Proprietary WCAP-12093, Evaluation of Pressurizer Surge Line Transients Exceeding 320 F for Beaver Valley Unit 2, for Review by 900901.Proprietary Rept Withheld (Ref 10CFR2.790(b)(4))
ML20059E7631990-08-0101 August 1990
Provides Results of Util Evaluation of Licensed Operator Requalification Exam Conducted During Wks of 900709 & 16. Crew That Failed to Meet Expected Performance Level Has Been Successfully Upgraded & re-evaluated to Be Satisfactory
ML20059B8141990-08-0101 August 1990
Requests Exemption from 10CFR26 Re Fitness for Duty Program & 10CFR73 Re Physical Protection of Plants & Matls Concerning Unescorted Access Requirements for Nuclear Generating Stations
ML20056A3471990-07-31031 July 1990
Responds to NRC Bulletin 90-001.Items 1 Through 5 of Requested Actions for Operating Reactors Completed
ML20056A1841990-07-27027 July 1990
Forwards Revised Methodology for Achieving Alternate Ac for Plant,Per 900720 Telcon
ML20055H2581990-07-25025 July 1990
Forwards Decommissioning Rept, Per 10CFR50.33(K) & 50.75(b)
ML20055F7061990-07-0909 July 1990
Responds to NRC Re Dcrdr Requirements as Specified in Suppl 1 to NUREG-0737.DCRDR Corrective Actions Implemented & Mods Determined to Be Operational Prior to Startup Following Seventh Plant Refueling Outage
ML20055D3871990-07-0202 July 1990
Provides Info Re long-term Solution to Action Item 3 of NRC Bulletin 88-008,per 890714 & s.Util Will Continue to Monitor Temp in Affected Lines & Evaluate Results
ML20058K5031990-06-29029 June 1990
Discusses Use of Emergency Diesel Generators as Alternate Ac Source at multi-unit Sites,Per Licensee .Emergency Diesel Generator Load Mgt Methodology Evaluated to Meet Listed Criteria
ML20044A3661990-06-21021 June 1990
Forwards Application for Amend to License NPF-73,consisting of Tech Spec Change Request 44,changing Stroke Time to 60 for Inside Containment Letdown Isolation Valves.Change Determined Safe & Involves No Unreviewed Safety Issue
ML20043G6811990-06-14014 June 1990
Forwards Application for Amends to Licenses DPR-66 & NPF-73, Revising Tech Specs Re Electrical Power Sys - Shutdown & Ac & Dc Distribution - Shutdown
ML20043H9341990-06-14014 June 1990
Forwards Issue 1 to Rev 4 to Inservice Testing Program for Pumps & Valves. Issue 1 Removes Relief Requests Requiring Prior NRC Approval & Adds Certain Program Changes Permitted by ASME XI & Generic Ltr 89-04
ML20043G5981990-06-12012 June 1990
Forwards Monthly Operating Repts for May 1990 for Beaver Valley Units 1 & 2 & Revised Rept for Apr 1990 for Beaver Valley Unit 1
ML20043G6851990-06-12012 June 1990
Forwards Application for Amend to License DPR-66,consisting of Proposed OL Change Request 176,revising Tech Specs to Replace Current Single Overpressure Protection Setpoint W/ Curve Based on Temp
ML20043G7941990-06-12012 June 1990
Responds to NRC 900524 Request for Addl Info Re Proposed Operating License Change Request 156.Clarification of Magnitude of Confidence Level of Westinghouse Setpoint Methodology,As Specified in WCAP-11419,encl
ML20043G8001990-06-11011 June 1990
Forwards Application for Amend to License NPF-73,consisting of Proposed Operating License Change Request 41.Amend Deletes Surveillance Requirement 4.4.9.3.1.d
ML20043H0291990-06-11011 June 1990
Forwards Application for Amend to License NPF-73,consisting of Proposed OL Change Request 40,modifying Heatup & Cooldown Curves Applicable to 10 EFPYs Per WCAP-12406 Re Analysis of Capsule U from Radiation Surveillance Program
ML20043F5251990-06-0707 June 1990
Requests Temporary Waiver of Compliance from Tech Spec Limiting Condition for Operation Re Operability of Containment Isolation Valves During Quarterly Slave Relay Testing.Evaluation to Support Request Encl
ML20043F1361990-06-0404 June 1990
Advises That Chemistry Manual Chapter 5P1, Enhanced Primary to Secondary Leakrate Monitoring Program for Unit 1,per 880328 Request to Recommit to Item C.1 of NRC Bulletin 88-002
ML20043B5971990-05-18018 May 1990
Advises of Delay in Hiring Independent Safety Evaluation Group Replacement to Maintain Five Permanent Personnel Onsite,Per Tech Spec 6.2.3.2.Replacement Will Be Provided within 30 Days of Retirement of Engineer on 900531
ML20043B0511990-05-15015 May 1990
Responds to Telcon Request for Addl Info Re Elimination of Snubbers on Primary Component Supports.Probability of Case B/G Event Extremely Small & Does Not Represent Realisitic Scenario
ML20043B1921990-05-11011 May 1990
Forwards Cycle 8 & Cycle 2 Core Operating Limits Rept,Per Tech Spec 6.9.1.14
ML20042G9761990-05-0808 May 1990
Responds to NRC 900226 Ltr Re Violations Noted in Insp Repts 50-334/89-80 & 50-412/89-80.Corrective Action:Maint Work Request Program Being Upgraded to Include Responsibilities of Nuclear Const Dept & Will Be Issued by 900601
ML20042G8541990-05-0303 May 1990
Forwards Technical Review,Audit Summary & Operability Assessments Re Potentially Invalid Leak Detection Tests Used as Alternative for Amse Section XI Hydrostatic Tests
ML20042G9071990-05-0101 May 1990
Forwards Annual Financial Repts for Duquense Light Co,Ohio Edison Co,Pennsylvania Power Co,Centerior Energy Corp & Toledo Edison Co,Per 10CFR50-71(b)
ML20042F1381990-04-30030 April 1990
Advises That Final SER for Implementation of USI A-46 Will Be Delayed Until Late 1990
ML20042F0991990-04-20020 April 1990
Forwards Response to Request for Addl Info Re Second 10 Yr ISI Program
ML20012F5951990-04-10010 April 1990
Forwards Monthly Operating Repts for Mar 1990 & Revised Operating Data Rept & Unit Shutdown & Power Reductions Sheets for Jan 1990
ML20042E1471990-04-0404 April 1990
Forwards Application for Amends to Licenses DPR-66 & NPF-73, Consisting of License Change Request 174/36,updating Staff Titles to Reflect Nuclear Group Organization
ML20012F6021990-03-30030 March 1990
Submits Supplemental Response to Station Blackout Rule for Plant,Per NUMARC 900104 Ltr.Summary of Changes to Condensate Inventory of Dhr,Effects of Loss of Ventilation, Control Room HVAC & Reactor Coolant Inventory Listed
ML20012E3091990-03-23023 March 1990
Forwards Response to 900308 Request for Addl Info on Reg Guide 1.97 Re Variable for Steam Generator wide-range Level Instrumentation
ML20012E3451990-03-23023 March 1990
Submits Addl Info for Exemption from General Design Criteria GDC-57,including Background Info Describing Sys Operation & Addl Bases for Exemption Request.Simplified Recirculation Spray Sys Drawings Encl
ML20012D6491990-03-19019 March 1990
Requests Retroactive NRC Approval of Temporary Waiver of Compliance Re Tech Spec Limiting Condition for Operation 3.8.2.1 on Ac Vital Bus Operability.Sts Will Be Followed When Inverters Not Providing Power to Vital Bus
ML20012E4091990-03-16016 March 1990
Forwards Inservice Insp 90-Day Rept,Beaver Valley Power Station Unit 1,Outage 7, for 880227-891221,per Section XI of ASME Boiler & Pressure Vessel Code 1983 Edition Through Summer 1983 Addenda,Section XI
ML20012D6181990-03-15015 March 1990
Responds to NRC 900215 Ltr Re Violations Noted in Insp Repts 50-334/89-23 & 50-412/89-22.Corrective Actions:Safety Injection Signal Reset & Plant Returned to Presafety Injection Conditions & Crew Members Counseled
ML20042D7401990-03-14014 March 1990
Forwards Corrected Annual Rept of Number of Personnel Receiving Greater than 100 Mrem & Associated Exposure by Work Function at Plant for CY89.
ML20012D5801990-03-13013 March 1990
Forwards Correction to First 10-yr Inservice Insp Program, Rev 2 to Relief Request BV2-C6.10-1 Re Recirculation Spray Pump - Pump Casing Welds & Relief Request Index
ML20012D6221990-03-13013 March 1990
Forwards Response to Generic Ltr 89-19, Resolution to USI A-47. Recommends All Westinghouse Plant Designs Provide Automatic Steam Generator Overfill Protection to Mitigate Main Feedwater Overfeed Events
ML20012C1791990-03-0909 March 1990
Responds to NRC 900207 Ltr Re Deviations Noted in Insp Repts 50-334/89-25 & 50-412/89-23.Corrective Actions:Written Request Initiated to Identify Unit 2 post-accident Monitoring Recorders in Control Room & Recorders Labeled
ML20012E0911990-03-0505 March 1990
Lists Max Primary Property Damage Insurance Coverages for Plant,Per 10CFR50.54(w)(2)
ML20012B7051990-03-0202 March 1990
Responds to NRC 900131 Ltr Re Violations Noted in Insp Repts 50-334/90-05 & 50-412/90-04.Requests Withdrawal of Violation Re Stated Transport Problem & Reclassification as Noncompliance,Per 10CFR2,App C,Section G
1990-09-07
[Table view] |
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2NRC-6-126 Beaver Valley No. 2 Unit Project Organization S.E.G. Building Telecopy ( 12) Ext.160 P.o. Box 328 Dec. 19, 1986 Shippingport, PA 15077 Mr. Harold R. Denton Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. Peter Tam, Project Manager Division of PWR Licensing - A Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Evaluation of Superheated Stean Blowdown on the Environmental Qualification of Equipnent - Supplemental Information
REFERENCE:
2NRC-6-099, dated September 20, 1986 Equipnent Qualification Report - Environmental Qualification of Class 1E Electrical Equipnent Gentlenen:
In response to your infonnation request during a November 25, 1986 telecon between the NRC and BVPS-2 Project, attached are six (6) copies of supplenental information regarding the evaluation of superheated stean blowdown on the Environnental Qualification of BVPS-2 equipnent. This response supplenents Appendix E of the reference and provides 1) additional infonnation on the con-puter codes utilized in the superheat evaluation and 2) a conparison with simi-Iar conputer codes as identified oy the NRC in the Novenber telecon. This infonnation is supplied to the NRR staff to assist in their review of BVPS-2 evaluation of superheated stean blowdown.
Should there be any questions regarding this matter, please contact Mr.
E. T. E11mann at (412) 393-7895.
DUQUESNE LIGHT COMPANY By ,
Sa m mne l
v44 ft b 8612310023 861219 (1 PDR ADOCK 05000412 PDR A
United States Nuclear Regulatory Commission Mr. Harold R.'Denton, Director . _
Evaluation of Superheated Steam Blowdown on the Environnental Qualification of Equipnent - Supplemental Information Page 2 KEW/ijr NR UPL/ INFO At nts AR cc: Mr. P. Tam, Project Manager Mr. J. Bealle, NRC Resident Inspector INP0 Records Center (w/o)
NRC Document Control Desk (w/o)
h
. Supplemental Information Regarding the Evaluation of Superheated Stean Blowdown on the Environmental Qualification of Equipment INTRODUCTION On Novenber 25, a conference call was established anong representatives of the NRC, DLC and SWEC. The purpose of the call was to address several NRC Staff Reviewer questions regarding the environmental qualification of equipment.
A discussion of each question is contained herein.
DISCUSSION THREED Computer Program The THREED computer progran is used for both subcompartment and pipe break outside contairinent analyses. THREED has been benchmarked against RELAP4/ MOD 5 in Reference 2 and against COMPARE /M000 in Reference 3 as part of its qualifi-cation procedure. Results have Deen taken fron both references and are shown in Attachnents 1 and 2, respectively . Note that both pressures and tenper-atures compare very closely in all cases.
Reference 4 calculation perfonns the Main 5tean Valve House (MSVH) pipe break analysis. Seven pages were extracted from Reference 4 and are shown in Attach-ment 3. Pages 9 and 11 show the MSVH model in schenatic form, and Pages 62-66 are the " echo" input to THREED with handwritten explanations of each important input witn eight percent revaporization as shown in tne heat sink section of the input oata. This correlation def aults to natural convection when the par-tial pressure ratio of stean to total pressure is less than 0.013see Attach-ment 4).
TAP-A Computer Program The TAP-A computer progran is a general thermal analyzer. It does not contain
" built-in" convection subroutines as convection must be input as part of the general input data, convection coefficient of four times the maximum Uchida value (1200 Btu /hr-f tp-F*) is used in parallel with a forced convection model up to the time the equipment surf ace reaches the dewpoint. At this point con-densation stops and forced convection continues until blowdown tenninates.
When blowdown enas, forced convection defaults to natural convection.
The following taDie summarizes the results of all equipment that has had tem-perature predictions by thennal analysis:
n l Peak Calculated Surface Qualified Analysis V Item Temp. (*F) Temp. (*F) Reference No. Comment MSIV 273 340 6 Vendor Supplied Trip Solenoids Limit Switches MSIV 193 340 6 Vendor Supplied Terminal Blocks Wire Lugs MSIV Ficxible 350 440 6 Vendor Supplied Conduit Inner Surface Ctble, Rigid Conduit 431 450 7 See Appendix E Inner Surface Terminal Block 352 450 7 See Appendix E Limit Switch 340 365 7 See Appendix E MSIV 136 200 8 Includes Heat Pressure Transducer Generation Attachment 5 shows a typical thermal model of a cable, limit switch housing, and terminal strip and the computer input for all three items. Key inputs Q have been identified on the input sheet.
The THREED and TAP-A computer programs were successfully used for nearly all of the subcompartment., pipe break outside containment (PBOC), and thermal lag analyses for other SWEC designed nuclear units.
REFERENCES 1l 1. SWEC Computer Program, "THREED - A Subcompartment Transient Response Code," NU-092U
- 2. SWEC Calculation THREED-US(B)-008-0, " Compare Results of THREED and RELAP4/ MODS Computer Codes Using "The Metcalf Run" as a Basic Input Guide," 6-12-79 (Attachment 1)
- 3. SWEC Calculation THREED-US(B)-011-0, " Comparison of THREED, Rev. 11 (NU-92) and COMPAhE/ MODO Results for NRC Standard Problems," 7-10-79 (Attachment 2)
- 4. SWEC Calculation No. 12241-US(B)-128-8, "HELB in MSVB for Equipment i Qualification," 8-13-86
- 5. " TAP-A - A Program for Computing Transient or Steady-State Temperature Distributions," Westinghouse Astronuclear Laboratory, WANL-TME-1872, December 1969 l 6. SWEC Calculation No. 12241-US(B)-202-1, 8-22-86 9627-12241-B4 2
4
- 7. . SWEC Calculation No. 12241-US(B)-206-0, 8-19-86
- 8. SWEC Calculation No. 12241-US(B)-196-0, 3-6-86 ATTACHMENTS
- 1. Page 9 from Reference 2 4.
- 2. Pages 4 and 5 from Reference 3 4
- 3. Pages 9, 11, 62-66 from Reference 4
- 4. Discussion of Uchida Model for Condensation Heat Transfer (2 pages)
- 5. Pages 10 and 27 from Reference 7 i
1 l
1 I
j
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- C0630070 CVPS2 HSVH 14 NDOE HODEL - 1.0 SQUARE FOOT ARES HIGH ENERGY LINE BREAM THREED 19 DEC 1985 13:58:31 PAGE 1 S & H ENGR CORP NU-092 SUSC2PARTHENT ANALYSIS PROGRAH THREED.VER13. LEV 00 CREATED 84.283 10:55 49 UNIT 10 UNIT 55 (SEQ 1) INPUT ECHO 1 2 3 4 5 6 7 8 y 12345678901234567890123456789012345678901234567890123456789012345678901234567890 1 BVPS2 HSVH 14 N00E HODEL - 1.0 2QUARE FOOT AREA HIGH ENERGY LINE BREAN 1 q N 2 a 2 g g 3 a 3 q g 4 mPROBLEH DIHENSION CARD 4 5 a 5 6 m 6 7 1 15 5 14
- 33 1 0 6 0 13 7 O 8 m 8 @
10 0 1 0 100 (NCI 10 11 m 11 y 12 m 12 13 mIIPLICIT/ EXPLICIT COEFFICIENT CARD 13 14 a 14 15 m ,
15 m 16 1.0 s 16 g 17 a 17 w 18 m 18 19 19 eTIHE STEP CONTROL DATA CARDS Q 20 m 20 21 m 21 22 I 22 10 10 0 0 0.0001 0.00001 0.02 23 50 2 0 0 0.001 0.0001 0.5 23 24 50 2 0 0 0.01 0.001 2.0 l 24 M N 25 25 2 0 0 0.02 0.001 4.0 25 % y 26 10 10 0 0 0.05 0.001 10.0 26 A 27 28 10 10 0 0 5 10 0 0 0.1 0.2 0.01 0.01 50.0 100.0 27 28 K 29 10 10 0 0 0.5 0.01 200.0 29 \
30 5 10 0 0 1.0 0.1 1800.0 30 d 31 50 2 0 0 0.01 0.001 1801.0 31 ID Nj 32 33 25 4 0 0 0.02 20 2 0 0 0.05 0.001 1805.0 0.001 1810.0 32 33 g >
q 34 10 2 0 0 0.1 0.01 1820.0 34 35 5 10 0 0 0.5 0.01 1850.0 35 36 20 10 0 0 1.0 0.1 3700.0 36 37 h
37 38 m
39 mTRIP CONTROL DATA CARDS 39 40 m 40
~
41 a 41 D 42 1 0 0 3600.0 0.0 42 @
43 43 44 1
2 0
1 14 0 0.0 0.15 0.0 0.0 44 ' $
45 2 2 14 0.15 0.0 45 46 2 3 14 0.15 0.0 46 Y 47 m 47 N
-; 48 m 48 49 q
49 mHODAL DATA CAROS 4 7 50 m 50 12345678901234567890123456789012345678901234567890123456789012345678901234567890
y ..
R0630870 CVPS2 HSVH 14 NODE H00EL - 1.0 SQUARE TOOT ARES HIGH ENERGY LINE BREAN THREE3 19 CEC 198513:58:31 PAGE 2 S & H ENGR CORP FU-092 SUSCOMPARTHENT ANALYSIS FROGRAH THREED.VER13. LEV 00 CREATED 84.283 10:55:49 UNIT 10 UNIT 55 (SEQ ll Its'UT ECHO 1 2 3 4 5 6 7 8 '
12345678901234567890123456789012345678901234567890123456789012345678901234567890
, Jeuh (PM d & LM. %
51 e Tewfffl ) g g * ({P) 6pd)
Vf "&ub r Fm%~ 51 M M l 52 q 2 53 14.36 14.36 120.0 120.0 1.0 1.0 1326.0 1326.0 33.25 33.25 8.50 8.50 0.0 0.0 0
0 0.0 0.0 52 53 N
54 14.36 120.0 1.0 1581.0 33.25 0.50 0.0 0 0.0 54 N 55 14.36 120.0 1.0 3642,0 23.33 9.92 0.0 0 0.0 55 M 56 14.36 120.0 1.0 3450.0 23.33 9.92 0.0 0 0.0 56 b-4
/ 57 14.34 120.0 1.0 4444.0 23.33 9.92 0.0 0 0.0 57 .
58 14.34 120.0 1.0 2835.0 14.67 8.66 0.0 0 0.0 58 I 14.36 120.0 1.0 2676.0 14.67 8.66 0.0 g
59 60 14.36 120.0 1.0 3530.0 14.67 8.66 0.0 0
0 0.0 0.0 59 60 O
61 14.36 120.0 1.0 5405.0 0.00 14.67 0.0 0 0.0 61 42 14.36 120.0 1.0 5127.0 0.00 14.67 0.0 0 0.0 42
- 63 14.34 120.0 1.0 6588.0 0.00 14.67 0.0 0 0.0 63 64 14.36 120.0 1.0 5149.0 0.00 16.00 0.0 0 0.0 64 b M / ** M lI65 14.36 103.0 1.0 1.0E20 0.00 41.75 0.0 0 0.0 65 48 i= HEM ndel JhdW T& $$ $
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72 10 11 0 0 95. .051 1.867 1.885 2 1.0 0 0.0 7.28 1.0 72 73 11 12 0 0 154. .045 1.433 1.402 2 1.0 0 0.0 7.28 1.0 73 74 11 12 0 0 95. .053 1.895 1.870 2 1.0 0 0.0 7.28 1.0 74 75 7 10 0 0 222. .029 .801 .001 2 1.0 0 0.0 14.67 1.0 75 76 8 11 0 0 211. .030 .849 .849 2 1.0 0 0.0 14.67 1.0 76 g 77 9 12 0 0 281. .024 .817 .817 2 1.0 0 0.0 14.67 1.0 77 78 12 13 0 0 24. .131 2.387 2.406 2 1.0 0 0.0 3.59 1.0 78 N 79 7 6 0 0 91. .072 1.395 1.419 2 1.0 0 0.0 19.00 1.0 79 Q y 80 7 8 0 0 56. .084 1.822 1.840 2 1.0 0 0.0 19.00 1.0 80 81 8 9 0 0 91. .076 1.433 1.401 2 1.0 0 0.0 19.00 1.0 81 82 8 9 0 0 56. .090 1.848 1.826 2 1.0 0 0.0 19.00 1.0 82 I M 83 84 6
5 9
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.670
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.671 2
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0 0.0 0.0 23.33 23.33 1.0 1.0 83 84 Q 85 4 7 0 0 280. .023 .670 .670 2 1.0 0 0.0 23.33 1.0 85 86 4 5 0 0 104. .063 1.398 1.421 2 1.0 0 0.0 28.29 1.0 86 87 4 5 0 0 64. .075 1.871 1.888 2 1.0 0 0.0 28.29 1.0 87 88 5 6 0 0 104. .067 1.435 1.404 2 1.0 0 0.0 28.29 1.0 88 89 90 5 6 0 3 6 0 0
0 64.
186.
.079
.033 1.898
.400 1.875 2 1.0
.328 2 1.0 0 0 0.0 0.0 28.29 33.25 1.0 1.0 89 90 d
91 2 5 0 0 156. .040 .366 .314 2 1.0 0 0.0 33.25 1.0 91
~
92 1 4 0 0 156. .040 .392 .325 2 1.0 0 0.0 33.25 1.0 92 Y 93 1 2 0 0 78. .153 .336 .336 2 1.0 0 0.0 38.50 1.0 93 94 2 3 0 0 73. .165 .336 .336 2 1.0 0 0.0 38.50 1.0 94 95 96 3 14 2 14 0
0
-5
-4 48.
40.
.087
.104 2.224 2.226 1.632 1.638 2
2 1.0 1.0 0
0 0.0 39.12 0.0 39.12 1.0 1.0 95 96 A
97 1 14 0 -3 40. .104 2.226 1.638 2 1.0 0 0.0 39.12 1.0 97 98 3 14 0 -5 37. .100 2.226 1.636 2 1.0 0 0.0 39.12 1.0 98 N
~
99 1 14 0 -3 37. .108 2.226 1.636 2 1.0 0 0.0 39.12 1.0 99 1
- 100 3 14 0 -5 48. .087 (2.224 1.632 2 1.0 0 0.a 39.12 1.0 100 12345670901234567890123456789012345678901234567890123456789012345678901234567890 @
W L _ _
L
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) -
C:0630B d BVPS2 HSVH l'4 NODE HODEL - 1.0 SQUARE FOOT AREA HIGH ENERGY E BREAN THREEO 19 DEC 1985 13:58:31 PAGE 3 S & H ENGR CORP NU-092 SUBCOiFARTHENT AriALYSIS PROGRAH THREED.VER13. LEV 00 CREATED 84.283 10:55:49 UNIT 10 UNIT 55 (SE9 1) ItPUT ECHO 1 2 3 4 5 6 7 8 12345678901234567890123456789012345678901234567890123456789012345678901234567890 101 2 14 0 -4 40. .104 2.226 1.638 2 1.0 0 0.0 39.12 1.0 101 102 1 14 0 -3 40. .104 2.226 1.638 2 1.0 0 0.0 39.12 1.0 102 103 0 10 1 0 1.00 0.0 0.0 0.0 0 1.0 0 0.0 7.28 1.0 103 N 104 a 105 e 10%
105 N
106 mH00AL DIFFERENTIAL PRESSURE CARDS} 106 b 107 m 107 5:*
108 a 108 y 109 1 10 14 109 ,
110 2 7 14 110 111 112 3
4 4
12 14 14
( 111 112 g
113 5 9 14 113 @
114 6 6 14 114 115 m 115 116 m / g ) 116 111 117 118 nFILL a TABLE DATA CARDS (wi( E RtiC4 5 c / 118 C 119 120 m
24 h'l 1%g 6 2 -
119 120 ^
M) 121 0.0 1576.0 1.89E6 121 CD 122 5.0 1443.0 1.73E6 122 V 123 10.5 1332.0 1.60E6 123 124 14.0 1661.0 1.99E6 124 125 20.0 1374.0 1.65E6 125 126 25.0 1193.0 1.44E6 126 127 30.0 1071.0 1.29E6 127 128 40.0 904.9 1.09E6 128 129 50.0 807.9 9.73E5 129 130 60.0 748.0 9.01E5 130 N 131 70.0 710.0 8.55ES 131 g 132 77.5 691.2 8.32E5 132 133 85.0 640.8 7.80E5 133 134 90.0 588.4 7.22E5 134 ! ""
135 100.0 437.4 5.45ES 135 136 120.0 101.2 1.30E5 136 137 129.0 34.88 4.50E4 137 g 138 159.0 15.31 1.99E4 138 q 139 200.0 34.82 4.53E4 139 140 500.0 41.28 5.39E4 140 141 142 1000.0 1800.0 41.28 41.27 5.40E4 5.39E4 141 142 Q
143 1800.1 0.0 0.0 143 144 5000.0 0.0 0.0 144 g 145 a 145 146 m 146 N 147 148 mPASSIVE HEAT sit 0( DATA CARDS e
147 148 149 m 149 7 150 SINH 1-NODE 1 150 12345678901234567890123456789012345678901234567890123456789012345678901234567890 D
b
fi q k) p ' **
'i C0630870 BVPS2 HSVH 14 N00E HODEL - 1.0 SQUARE FOOT AREA HIGH ENERGY LINE BREAN THREED 19 OEC 1985 13:58:31 PAGE C C -
g' S & H ENGR CORP ttJ-092 SUDC0tFARTHENT ANALYSIS PROGRAH THREED.VER13. LEV 00 CREATED 84.283 10:55:49 UNIT 10 UNIT 55 (SEQ 1) ItPUT ECHO 1 2 3 4 5 6 7 8
, 12345678901234567890123456789012345678901234567890123456789012345678901234567890 151 13 1 0 0.0 275.0 1 0 151 in 154 l' *
%u W), typed lg 154
~
N 155 156 1 1 1 .08 0 0 0 1.0 SItH-2 N00E2
[
7 155 156 N
g 157 13 1 0 0.0 258.0 2 0 157 /
158 13 1.0 158 f 159 160 1
F 159 160 161 1 1 1 .08 0 0 0 1.0 161 O pf 162 163 SItH-3 N00E3 13 1 0 0.0 305.0 3 0 162 163 164 13 1.0 164 hg j 165 166 1
F 165 166 1 167 1 1 1 .08 0 0 0 1.0 167 69 168 IPE4-N00E4 168 169 13 1 0 0.0 919.3 4 0 169 m y( ( f
, ): MCbt & Co **f!5 'A 3 0 0 0 1.0 73 174 SIPMS-NODES 174 175 13 1 0 0.0 743.3 5 0 175
- l'1c ;. s.1x niv.I v v. 6k ::'
178 F 178 >=4 h 179 180 l' 1 .08 0 0 0 1.0 SI E6-NODE 6 179 180 M'
181 13 1 0 0.0 1018.0 6 0 - 181 O
!N 184 F
~ l= [4r/l / reve/W788 184 g ,
185 186 1
SI -t00E7 0 0 1.C 70 185 186 M
187 13 1 0 0.0 603.8 7 0 187 4 188 13 1.0 108 l 189 1 109 190 F 190 NN
~
191 1 1 1 .08 0 0 0 1.0 191 192 Site <S-NODE 8 192 l 193 13 1 0 0.0 450.32 8 0 193 pj 194 13 1.0 194 l 195 195 196 1
F 196 Nl '
197 1 1 1 .08 0 0 0 1.0 197 198 SINH 9-t00E9 198 199 13 1 0 0.0 651.9 9 0 199
- 200 13 1.0 200 12345678901234567890123456789012345678901234567090123456789012345678901234567890 D
se
]' R06308 LVPS2 HSVH l'4 NOCE HDDEL - 1.0 SCUARE FOOT AREA HIGH ENE"GY E BREAM THREED 19 [EC 1985 13:58:31 PAGE 5 U -
5 & H ENGR CORP NU-092 SUSC0lFARTHENT ANALYSIS PROGRAH THREED.VER13. LEV 00 CREATED 84.283 10:55:49 UNIT 10 UtiIT 55 (SEQ 11 ItPUT ECHO 1 2 3 4 5 6 7 8 12345678901234567890123456789012345678901234567890123456789012345678901234567890
'{f 201 202 1
F 201 p 202
'- 203 1 1 1 .08 0 0 0 1.0 203 N 204 205 SITE 10-N00E10 0.0 1359.6 10 204 N
, p.
~~
206 13 1 0 0 205 y 13 1.0 206 g 207 1 207 208 F *
/ 208 5 209 1 1 1 .08 0 0 0 1.0 209 210 SITE 11-N00E11 210 O 211 13 1 0 0.0 1124.4 11 0 211 @
212 13 1.0 212
... 213 1 213 214 F 214 215 1 1 1 .08 0 0 0 1.0 215 216 SITE 12-N00E12 216 217 13 1 0 0.0 1548.8 12 0 217 218 13 1.0 218 m 219 220 1
F 219 220 W W
221 1 1 1 .08 0 0 0 1.0 221 222 SITE 13-N00E13 222 223 13 1 0 0.0 2682.7 13 0 223 224 13 1.0 224 225 1 225 226 F 226 227 1 1 1 .08 0 0 0 1.0 227 N 228 229 a
a 228 229 N
230 mDATA C0ttION TO HEAT SITES 230 M 231 e 231 232 a 232 I 233 0.0 233 234 0.0 234 N 235 120.0 FF 235 236 0.79 24.93 ' CONCRETE'/ 236 237 [ND OF HEAT SLAB DATA 237 12345678901234567090123456789012345678901234567890123456789012345678901234567890 < EOF) COPIED TO UNIT 5 H/0 CitTS Q N
, N o
} AXAGMwr 4 U2 .,
=
0 Since the mole fraction of steam is equivalent to the pressure fraction of steam, Ps/Pt, where Ps is the partial pressure of steam and Pt is the total pressure of the mixture, a graph of heat transfer coefficient as a function of the pressure fraction of steam can be generated. This graph is presented in Figure 3.2.2B-2 It should be noted in the transformation from Figure 3.2.2B-1 to Figure 3.2.2E-2 that the units of heat transfer coefficient were changed from (Kcal/m2-hr-deg C) to (Btu /f t2-br-deg 7) .
o 300 -
Yu onUC =~.
SY a
(, 100.
9% . .-
0
- d e
e~ os .
o 0.2 0 .4. 0.6 0.8 1.o Ps/Ft Fiy ,e 3.2.2B-2 Effoot of Sie::m Fressu-e Fraction Variation on Heat Transfer Coefficient The use of the data presented in Reference (1) is ccnservative.
The reason for this conservatism is that the test sections used in obtaining the heat transfer coefficient were small while the actua) vertical walls in the reactor containment are very large.
(2) shows that for natural convection on short vertical O Reference plates the flow is predominantly laminar, while for large vertical plates , a transformation to turbulence occurs. The occurrence of turbulent flow means that the heat transfer L
- I ATrAd(MEwr 4 2/2. ; -
\ ,
will be greatly increased. Thus, the heat transfer coefficients 10' coefficients presented in Reference (1) must be conservative when applied to large vertical walls, since they do not design In addition, the accountbasisfor l turbulent heat transfer effects. extremely turbulent state in the accident will result in an
'l containment during che time to reach the peak containment 1 pressure.
ccndensation heat transfer Increasing ~ the value of the coefficient means that more energy is absorbed by the containment structure during the DBA. This in turn means that the peak I pressure in the containment will be lowered. '1hus the use of an artificially low natural convection condensation heat transfer coefficient means that the resulting calculated peak pressure l will be artificially high.
curve of heat transfer coefficient shown in Figure 3.2.2B-2 The can be analytically expressed by the following relation:
h= (A/3.25) * (Ps/Pt) If 0.01 5(Ps/Pt) 50.19 or I h= A*exp [-3. 5* (1 - Ps/Pt) ]
where A is the input value for heat transfer coefficient If (Ps/Pt) >0.19 of pure steam (300 in Figure 3.2. 2B-2 above)
If (Ps/Pt) is less than 0.01, the minimum value of heat transfer transfer coefficient that is used is the natural convection heat I coefficient for pure air (about 1. 8) .
References:
' 1. Uchida, H; Ogana and Togo, Y; " Evaluation of Post-Incident Cooling Systems of Light j
Nater Power Reactors," 3rd U.S. International l
' conference en the Peaceful Uses of Atomic Energy, vienne, May, 1964 (Japan p/436) .
l
- 2. McAdams, W. H., " Heat Transmission,"
3rd ed., McGraw-Hill, New York, 1954.
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