|
|---|
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:NRC TO ENGINEERING/CONSTRUCTION/CONSULTING FIRM
MONTHYEARML20247N1321989-09-18018 September 1989
Final Response to FOIA Request for Records.App a Records Available in Pdr.App B Record Encl & Available in PDR
IA-89-382, Final Response to FOIA Request for Records.App a Records Available in Pdr.App B Record Encl & Available in PDR1989-09-18018 September 1989
Final Response to FOIA Request for Records.App a Records Available in Pdr.App B Record Encl & Available in PDR
ML20154A1521988-08-17017 August 1988
Final Response to FOIA Request for Documents.Forwards Documents Listed in App A.Documents Also Available in Pdr. App B Documents Totally Withheld (Ref FOIA Exemption 5).App C Documents Partially Withheld (Ref FOIA Exemption 5)
ML20153F1951988-08-10010 August 1988
Partial Response to FOIA Request for Documents.App a Documents Available in Pdr.Nrc Reviewing Item F of Request
ML20237B8171987-12-14014 December 1987
Final Response to FOIA Request for Documents,Including Johnson Ltr to NRC Transmitting Rev 1 to LER 85-005.Forwards App B Document.App a & B Documents Also in Pdr.Nrc Not in Possession of Item 2 of Request
IA-87-807, Final Response to FOIA Request for Documents,Including Johnson Ltr to NRC Transmitting Rev 1 to LER 85-005.Forwards App B Document.App a & B Documents Also in Pdr.Nrc Not in Possession of Item 2 of Request1987-12-14014 December 1987
Final Response to FOIA Request for Documents,Including Johnson Ltr to NRC Transmitting Rev 1 to LER 85-005.Forwards App B Document.App a & B Documents Also in Pdr.Nrc Not in Possession of Item 2 of Request
ML20236V3351987-12-0101 December 1987
Final Response to FOIA Request for SECY-87-146 & SECY-87-164.App a Document Partially Withheld (Ref Exemtion 5).App B Document Totally Withheld (Ref FOIA Exemption 5)
ML20245C3591987-10-29029 October 1987
Requests Brief Note Expressing Desire to Remain on Mailing List.Response Requested Before 871120
ML20238D1401987-09-0909 September 1987
Final Response to FOIA Request for Documents Re 790313 Order Shutting Down Facility Due to Concerns Re Over Stresses in safety-related Piping Sys & Supports.Forwards App E Documents.Documents Also Available in PDR
ML20237H6231987-08-20020 August 1987
Partial Response to FOIA Request for Documents Re Plant Pipe Stress.Forwards App B Documents.App a Documents Available in Pdr.App B Documents Being Made Available in PDR
ML20212K7171986-08-14014 August 1986
Approves Withholding of Proprietary Info Re Whipjet Program (Ref 10CFR2.790),per Util 851010 Request & Rl Cloud Assoc, Inc & Recipient 851009 Affidavits
ML20203H1741986-07-28028 July 1986
Final Response to FOIA Request.Forwards Documents Listed in App B.App a & B Documents Available in PDR
IA-86-278, Partial Response to FOIA Request.Documents Listed in Apps D & E Available in PDR1986-06-27027 June 1986
Partial Response to FOIA Request.Documents Listed in Apps D & E Available in PDR
ML20211L5281986-06-27027 June 1986
Partial Response to FOIA Request.Documents Listed in Apps D & E Available in PDR
ML20136E7231985-11-0707 November 1985
Responds to FOIA Request,Confirming 851001 Telcon Which Advised That NRC 850705 Response to 841214 FOIA Request Re Plant Final
IA-84-926, Responds to FOIA Request,Confirming 851001 Telcon Which Advised That NRC 850705 Response to 841214 FOIA Request Re Plant Final1985-11-0707 November 1985
Responds to FOIA Request,Confirming 851001 Telcon Which Advised That NRC 850705 Response to 841214 FOIA Request Re Plant Final
ML20133M6911985-07-0505 July 1985
Further Response to FOIA Request for NRC Internal Memos to Div of Licensing from May-Nov 1984,providing Draft Ser,Ser Sections & NRC Questions or Requests for Addl Info.App D Documents Encl.Documents Also Available in PDR
ML20126J9081985-03-0606 March 1985
Further Response to FOIA Request That All Internal Memos to Div of Licensing from May-Nov 1984 Which Provided Draft SER, SER Sections & Questions or Requests for Addl Info Be Placed in Pdr.App C Documents Placed in PDR
ML20128F9741985-03-0404 March 1985
Further Response to FOIA Request for All NRC May-Nov 1984 Memos to Div of Licensing Re Draft SER & SER Sections. Forwards App B Document.Document Also Available in Pdr. Document Partially Withheld (Ref FOIA Exemption 3)
1989-09-18
[Table view]
Category:OUTGOING CORRESPONDENCE
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
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
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
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
ML20205Q8311999-04-14014 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
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
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
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)
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
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
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
ML20155K4041998-11-0505 November 1998
Forwards Insp Repts 50-334/98-07 & 50-412/98-07 on 981006- 07.No Violations Noted.Overall Performance of Emergency Response Organization Was Good
1999-09-08
[Table view] |
Text
{{#Wiki_filter:fse, Fo1 R T70 us,0Nsir m l
[.
' P' . RESPONSE TO FREEDOM OF N '"^' I ! '' 2
'g eee..
j INFORMATION ACT (FOlA) REQUEST A CJ (
$[p - 9 jgg7
~
' DOCKET hvMBERisi vr oppsceam REQUESTER PART l.-RECORDS RELEASED OR NOT LOCATED ISee checked boxes) ~
No agency records subpset to the request have been located. ,
No additonal agency records subpset to the recivest have been located. N s
Agency records subpct to the request thyt are identifed in Appendu are sIready available for public inspection and coppng in the NRC Pdic Document koc l 1717 H Street, N.W. Washington, DC . g Agency records sub.ect to the reavest that are identifad in Appendix b_ are being made available for public inspection and copying in the NRC Public Docurm
]
Room.1717 H $treet, N.W., Washir<gton, DC, ia a folder under this FOIA number and reauester name. j The nonpropnetary version of the proposal (s) that you agreed to accept in a telephone conversation with a member of my staM is now bemg made avalable for public inspection and coving at the NRC Public Document Room,1717 H Street. N W., Washington, DC, in a folder under the FOIA number and requestar name.
Enclosed is informahon on how you may obtain access to and the charges for copying records placed in the NRC Pubhc Document Room,1717 H Street, N.W., Washington, DC.
Agency records subpet to the request are enclosed. Any applicable charge for copies of the records provided and payrnent procedures are noted in the comments section.
Records subpct to the request have been referred to another Federal agency 6es) for review and direct response to you.
I in view of NRC's response to the request, no further action is being taken on appeal letter dated i
PART H A-4NFOftMATION WITHHELD FROM PUBLfC DISCLOSURE Conain informaton in the requested records <a being wkhheld from pubhc d<sclosure pursuant to the FOIA exemptione described in and for tne reasons stated in Part it, sec- l tions B. C, and D. Any released portions of the documents for which only part of the record is being withbeid are being made available for public inspection and copying in !
i the NRC Pubhc Document Room.1717 H Street N W., Washington, DC, in a folder under this FOlA number and requester name.
Comrnents l
l 1
- a SIG - . DIRECTOR,InvTION O P- 5 AND RE l 4e ,
d, -
i J
l 8709100501 870909 NRcFoRM
- PDR FOIA SCHIJENCB7-470 PDR is mi
.- - -- _ _ ._ _ _ _ _ __ ______.__._______.____._______________________a
s 4 - 4. . , Re:- F0! A- 8'7 - 4 7 0 -
0' APPENDIX E D.
RECORDS MAINTAINED IN THE PDR UNDER THE ABOVE RE0 VEST NUMBER NUMBER DATE DESCRIPTION
- l. l-t% 79 %.~ o -{p b m R. R . H u Q ko E.ef. f % ,
W 4: 6 - v g Pem % % a ,
E"
'OOf N Sp a 3 os a a X t a ; N h e a. /a w M -
( HITS ho . # I V74 / N,;2 ) (M (vry. ) ,: u)/NM *.
L R f6 A/E k O a /A n w3f"- E (Sgup) i i
j 1
e
,q # ,/ NM
^*
l
, , L g % UNITED STAYES NUCLEAR REGULATORY Commission y~ ~ h !
i*d' D,, I) j # t REGION I gf j 5p f
$31 PARK AVENUE I c- "f~a/
t .aua er raussia. ecausvt.vwA i .o. 4
.o}
..... 18 JAN 1979 i
MEMORANDUM FOR: E. L. Jordan, Assistant Director for Technical Programs.
DROI, IE ;
THRU: h U J. Brunner, Chief, Reactor Operations and Nuclear L
Support Branch, RI FROM: R. R. Keimig,' Chief, Reacto" Projects Section #1, RO&NS Branch, RI
~T i
SUBJECT:
BEAVER VALLEY POWER STATION UNIT 1 (DOCKET NO. 50-334)
SAFETY INJECTION PIPING STRESS' ANALYSIS - REQUEST FOR
- ADDITIONAL TECHNICAL REVIEW (AITS NO. F14741H2)
'[ The licensee submitted LER 78-53 to Region 1 on October 27, 1978 to {
{c.J J'l report errors identified by the licensee's A/E in the piping stress- i TAH analysis performed for safety injection piping inside the containment.. l' The LER was supplemented by additional reports on November 9 and Decem-hn ber 6,1978. The reported errors were discovered during an A/E review l n
of the stress calculations after receipt of new information from the l wi NSSS vendor which corrected the weights of check valves installed in the l injection lines. l During our. review of these activities, we noted that the A/E had applied.
L two essentially equivalent computer programs, PIPESTRESS and NUPIPE, to ,
> ... the reanalyses of three of the one hundred and three lines reviewed, i The results of these analyses indicated an overstress condition in two M lines requiring modification of the piping supports. Additionally, the "Uh results cotained from NUPIPE and PIPESTRESS for the same lines differed
- significantly with each other and with the original design hand calcu-lations. Attempting to reconcile these differences, we discussed the analysis results with the A/E and informally with NRR: DOR Engineering gh".-"
Branch (Steve Hosford). Our discussion with NRR indicated that the magnitude of the differences in results could not be reconciled by only
' the differences in calculational methods used by the computer programs as was indicated by the A/E. While the two lines affected have been
- modified to accomodate the differences, we are concerned that, if the differences in supposedly equivalent analysis methods cannot be tech-nically reconciled, nonconservative results may have been previously applied to pipe supports designed for safety related piping.
CONTACT: .D. Beck man (488-1268)
- 3) foIg-#7M76 E// *
J Memorandum for E. L. Jordan 2 18 JAN 1979 We request that the information contained in the attachment to this memorandum be forwarded to the NRR: DOR Engineering Branch for their review. We recommend that they assess the information provided and establish whether further review or action appears necessary. Our concerns include:
- 1. Reconcilia' tion of the differing analysis results to assure that the design methods used are neither incorrect nor unconservative; and,
- 2. The need for further licensee review of piping potentially affected
- by any incorrect or nonconservative calculations.
Our discussions with the A/E, Stone and Webster, were conducted with Mr.
1-James Cumisky (Boston Office, 617-973-5685). Mr. Cumisky has indicated
'" ' a willingness to provide additional. information or answer questions re-
, ni i garding this matter.
i,
/ R. R. Keimig, Chief g
l , Reactor Projects Section No.1 RO&NS Branch l
Attachment:
Chronology of A/E Reviews / Reanalyses
?
I
[',j 1 J 1 ;
g 1 -
%ll l
1
.I l
)
l
. l 4
u__.__. m
e gi rd n 3d nd p o 5( e t i
- / sSn t 8st eSa s F 7 ncnE c e 0 oeiRi u 0
.itl Tf q . 8 oti Si w 1 N ah eE n l ceP g no il 0 RurrIi .e E cahPs sb s Ll t e s 0 0 0 0 0 5 as ea nd e 0 0 0 8 0 7 eh i e r 6 9 8 1
td et c 'e h t de l s s
t S
6 1 2 4 9 4
8 9
2 7
6 3
4 yy 1 4 i ns eu nanfl a ec e 4
Uh eonl op rs l c hi b
- nlih s td a oal c gi er w i n and o ti eei h e l a gh sd th l tit oun t A S r t ,a rr o , ou S r s) th ff I ef rE rt S wooP rIaopb wd Y o on L P nrP l a A oeU rh e N yi N ot bd A et e i e E l asd ew dh R l cenl ec
/ aihaod d a S Vl t h e it s W p S wz vt s E r pf S y oa e I eaoE nl r r V vs Ria pe t E aisT n r S R emeSda ea B sE e r d E e yP we at e 3 1 3 3 9 0
/ nhlI er n t 9 2 3 0 4 0 A itaPi e se a 1 6 4 5 4 0 n( vw e em se l 6 1 3 2 7 7 F dfa eo srs yg u 3 3 3 3 O c t re e l n l Y rtiden . aa a G ol eoris nr C O puhcelt ar -
~ L est w l a 0 re r eu r N rneses eg O s It ere t n R re unh r pit ui pp H oh C rt .ml S mi r ) o eS op e y9 c 0 s E c g M M l . 0eR R R nt1 o1hT n E E on .w tS E wi H H i
tr e 1. t al ,P t w o
T T a a2d n eI l pBeol P eh h s
+ + i up iib t T T T T s canlopit tadn s E E E E p l fe B B B B a ei pd p a oh O 0 D D n crtade c i ec ace st + + + +
swe) s SrnaI cP t e lk p p p p p s
es ea P us p e l l l l S l l u rt ,t dU s : S S S S S S S l tnRsenN e , 0 E a seAbl u ry 2 + + + + R + + v mSeioe l - E T geFWhfh sl I P d d d d S d d l nl W t sa S I a a a c E a a l i pS & e en - P o o c o P o o A ppP rn ro U l l i l I l i iuVe .ee ti 6" N D D D D P D D psBnwwe st :
oo w i e E esetldt ed n T hthS ene hd i O
Tit (bab TA L N
R ei7 3 8 5 7 Rei7 2 6 4 8 t -
TN a -
S rI 2, 4, 7, 7, TNa-S rI 7, 7, 2, 2, aI m EhtS 0 9 6 0 iS a Pt s -
EhtS 1 5 0 7 r r 1 1 4 2 Pt s - 1 1 4 1 a g Ii e"
'P wR6 Ii e" PwR6 v "6 o r
eep l n
^
bis aLS r E n n err u u dot R R ifs s E S ndP S oeI S 5 9 9 4 S 2 1 1 2 ctP Et 8 9 3 8 Et 8 8 4 8 .a Rl Ti 3 ,. 8, 4, 8, Rl Ti 7, 8, 3, 9, et e Su 0 9 6 2 h oh Su 1 7 2 7 t nt EB 1 2 3 3 EB 1 6 0 7 n P * *
- P I s 1 2 1 wah PA I s * *
- o t PA hsi sew s ns8
- 2 2 oe ir6 n 7 n 7 tt -
u t - u t - as5 RwnI 5 8 9 3 RwnI 0 6 4 6 l eiS 4 6 4 6 eiS 8 1 3 0 ue6 EN a- 9, 2, 9, 4, ENa - 7 6, 8, 3,
- P Iht6 Pt s Ui en r"
9 8 1
0 4
1 2
P Iht6 Ft s Ui en r"
1 1
5 1
0 4
7 1
lh btf t
a ,o rr NwRo NwRo 'e ao
- 2 E
vl t ouc bca aif E t P t 3 8 4 9 P t 8 2 8 9 era I l 8 3 9 8 I l 9 5 7 0 h a P n Uusu i
5, 2, 9, 6 Pn Uusu i
7, 6 7, 6, t pf NRAB 9 6 6 8 NRAB o
0 3 1 1
1 9
0 4
6 3
1 nn 2 2 2 iI s 1
1 1 e
* ) c
- ( se
. n e t r l
l e kl e F suf .
b 0 0 0 0 b F 0 0 0 0 a s0 0 0 0 8 a s0 isf e ws0 0 0 0 8 reiv oe8 6, 9, 8, 8, ws0 oe8 6, 9
, 3, 8, erdi l r1 6 4 9 t 9 l r1 6 4 9 9 sEwa lt 1 2 4 2 lt
_ AS0 1 2 4 2 aP ov AS0 Ihr
- yP s e bU Nnn
- M M d
edic oo R R E t nt E aais H H c ds T T i Sne
+ dSol
+ nEc
. T T T iR T T T T E
B E
B E
B E
B E
B E
B seelS "th O O D O O D uPi e 3 + + + lI ub 7
2 7
+ + + aPb
- p p p p - p p p p v o I l l l l I est S S S S S S S l
S l 1 l sias
- S S st" g
" + + + +
- e n 6
6
+ + + + rnei d d d d d t ehr e d d d set a n
a o
a a a e a a a a w e i l 1 0
i o
l o i n o o c o et rp l i i i heop L O 0 D O L D D n D-Tbf a ll
.. 3 j
~ 1 Although modifications were made to line'SI-72 which reduced the stress ;
to allowable values in both it and SI-72, the difference in the respec- l tive as built results raised the question of the accuracy and/or conser- l vatism of the PIPESTRESS program as applied to all the 103 lines analyzed. '
The f>llowing information, extracted from the S&W report to the licensee 7
on this matter discusses the three lines involved and the evaluation of each line's stress analysis results. The figures mentioned are attached. '
y, "The nodel run in NUPIPE 'and in PIPESTRESS are geometrically similar, r I however, the mass distribution and support stiffness are different. '
further, the method of force summation (intramodal) is different rj between PIPESTRESS and NUPIPE. NUPIPE utilizes more conservative ,
techniques for intramodal combinations of gener/Jiized loadings.
'l These newer techniques arose following establishment of BV1 Design 4 Criteria . . . .
The PIPESTRESS methods used were accepted dynamic analysis tech-niques for Beaver Valley 1 generation plants and are the basis for.
all computerized Category 1 pipe stress analysis done for' Beaver ,
Valley Unit 1.
Figure IA gives the hanger location and peak local stress vs.
sllowable from the NUPIPE model for line 6"-SI-20. Figure IB is a i
hetch of the hangers-pipe (SI-A-60/6"-SI-?,0. interface showing the l overstressed area. The table attached to this sketch identifies ,
i the d,1fferences in the hanger attachment lo@s resulting from the two different computer models. Based on the above, the Safety l l Injection line 6"-SI-20 is acceptable as desiped."
]
Discussions with S&W indicated that this acceptance was basedwpon ob.-
taining satisfactory stress values using the techniques committed to for -
the original design. The differences in NUPIPE and PIPESTRESS results ,
were attributed to NUPIPE using root mean square values for individual
.and total loads where the PIPESTRESS program algebraically comb.ines ;
individual loads. ',.
i The S/S report continues: >
j
{
l .
PFigures II A&B' give,the most highh stressed hanger, location and i l '
stresses resulting from the NUPIPE and PIPESTRESS runs on 6"-SI-73.
) ,
Eased on this data, ii"-SI-73 is acceptable as designed.
1 I *
( ,
b
/
(
> O'
~
l . t l ' .
t i
I
,a =
Q
\
1 Figures IIIA and B give'the most highly stressed hanger, location j and stresses resulting from the NUPIPE and PIPESTRESS runs for line 1 6"-SI-72. Based on this data, modification to hanger YC-1.C-H306A
^
(Figure IV) and the addition of hanger LSS-H is' required to be 2
' added to line 6"-SI-72".
The reasons given by S&W for the differences between the NUPIPE and j PIPESTRESS results were the same as those for 6"-SI-20. In these cases,
~
j the addition of the supports on 6"-SI-72 also affected the response of- 1 6"-SI-73 (as noted in the far right hand column of the previous tabulation) l resulting in both the NUPIPE and PIPESTRESS values being within code {
allowable values. !
' In conclusion, the S&W report states-
. "We believe that the remainder of the containment annulus piping is I
acceptable based on the fact that the pipe stress analysis section
! has comple'ted a review of seismic piping shown on the BP-3 series
. . drawings (annuluspiping). The review was limited to piping 21/2" OD to 6" OD because of the possibility that these sizes may havo -
c been ar.alyzed by the ' chart' method. .The attached tabulation (Table I) contains all the seismic lines falling between 21/2" and
, , , 6". This tabulationicontains 103 seismic lines of which 55 were ,
@ > reviewed and found acceptable. !
A large portion of this piping was analyzed during the "as built l
, review" .(in S974) using computer program PIPESTRESS. PIPESTRESS results areravailabler for all or portions of 45 of the (remaining)
,'(
...
- teldlated lines and are acceptable".
W '. On the basis of discussions with NRR: DOR Engineering Branch personnel.
E gjh ws consider additional technice3 review is necessary-to neconcile the diffennces in the' PIPESTRESS 'and NUPIPE results.- These discussions in- ,
dicated that the differenc{s appeared to be incongruous in light of ~
i theiF, knowledge of the two,. prograrra.
1 j
1 j
t .
l e
. , y ,
~
< g 5' , i
/
" ~'
- .s> ..t ,
s - 4 l
i l
Tec mica Analysis Corporation l 6723 Whittier Avenue. Suite 202. McLean, VA 22101 (703)883-3700
]
)
l July 21,19El DIEDOM OF INFORMATl0#
' bclREQUEsr Director, Office of Administration 0 1 U. S. Nuclear Regulatory Commission Wa shington, DC 20555 d] -
Subj ect : Freedom of Inf ormation Act Request f or Records
Dear Gentleman:
We are seeking a . copy of certain internal NRC memoranda, notes and log book entries related to the events associated with !
the March 13, 1979 NRC Order which shut down the Beaver Valley i Uni t i reactor due to concerns over stresses in saf e ty r elate d piping systems and their supports. We have been unable to find these documents in the Public Document Room at 1717 H Street. ;
I In accordance with the provisions of the FOIA, we request a j 1 copy of the documents identified herein. j 1
Unless otherwise noted below, the period of time of interest to us is October 26, 1978 through August 8, 1979 only. 'Ibe following documents or groups of documents are requested:
- 1. I&E Region 1 memos, notes or Daily Reports to Hg on an l Oct ober 26 telecon in which Duquesne Light Company !
orally reported an werstress condition in the Beav er l Valley 1, Docket 50-33 4 Assigned LER 7 8-53/OIP. The phone call was made to Mr. D. R. Haverkamp and Mr. A. N.
I Fasno at 1630 hours on October 26, 1978.
I
- 2. Any I&E Region I working notes, Daily Reports to Hg, l memos of phone calls or utility handouts (from the Inspector and Region 1 persons), related to discussions with Duque sne Light or Stone and Webster or NRC Bethesda on this subje ct during or f oll owing the i October 31-November 3, 197 8 I&E inspection. We have Re por t No. 50-334/78-30 indicating that W.J. Raymond performed the inspe ction and identifying the representatives of Duquesne Light Company and Stone and Webster that were contacted during the inspection.
Period of interest here is October 31 to Nwember 14, 1978.
9' g p ? 9 W W ~7 ,
1
g 7 '
4-t iL %- ; 4 1 ,,y r; , , '
,, .o. ,
s .
,- s D"
~'
'3, . 'Same. req u!sst 4:[ 2 abbve except related, to 3 Luque sne ' s t ' Interim LER dated Novesber 9,. 1978 and the 4 inspection II, .
coy sted by lI&E Inspaction Report 50-334/78-33. Pt;ti od of ir.terest here i n, Novemba c .9 to Decenber 6, 1978 ~ and J ncl udes the' I&E 2napectin's calls to Luq ue sne on 11/30, 12/1 and 12/5/78,.
$. Same. . as 2 above' except reltted to Duybesne's LER 78-ti3 / IT-0. Period ot" intuent in December 6 through Cecember 8,197 8.
- 5. Region I memoranda, notes > and lirjono calls to or from i
the NRR project manager and arry oth&r person in. NRC Bethesda regarding strer;s calculations on Beaver Valley saf ety r ela ced sy stems. Period of interest is December 8 th r ough De cember 17 antj incl udes phene calls of December 17. and 14 and R6gion 1 Daily Report to Hg on De cabe r . li , 1. 97 8.
6.' Jam'e rec ua st as 2 abov e except related to the inspe ction covered fy I&E Inspection Report 50-334/78-
- 34. Period of interrn itt December 18, 197 G th rough December 31, 1978 and includes December 22 6iscussions with NRR/ DOR personnel (e.g., Wiggingt n, 'Hosf ord, others). .
7.- Pr ov ide a copy of the concurrence page for th e NRC March 12,1979 Show Cause Order on Beaver vc11ey Unit 1 and the concurrence page for the liafety Evalua tion Report. which accompanies that oren. .
- 8. b*amt req ue st as i dbove exceot for the NRC August 6, 1970 Order . on Beav er Valley Unit 1. .
- 9. Frov iih. all mem !randa, notes or other documents on this s ub,N ei o rigi na ted, con curred in or signed by the Director of Systems Saf ety, NRR and the Chief of D0R Enginaerial Branch t o anyone in NRCt
- a. Ad:sising f or or against the March' 13, 1979 Order on Bem er Valley Unit 1,
- b. Recommending f or or against approval of an ceder teminating that March 13,1979 oider.
- 10. Provido a copy of the pages of the WRR Beaver Valley 1 Proj ect Manager's Log Book that have entries related to the concerns over stresces in the saf ety related piping systems (October 26, 1978 through August 8,197 9) .
1 2 'l j
[J'] a*? ', f I Y /
f g,)
>.(_ "'F eiwe' agree to pay the cost of _ fulfilling this request up - to If' a higher cost is projected, please call' me at 883-L$200.00
. 3706. <
Your prompt response t'o this request will be appreciated.
Sincer ely, Al Schwencer l
4 3}}