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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] |
Text
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June 13, 1985 Mr. Robert M. Keller, Chief Section 1C (Operator Licensing)
Division of Project and Resident Programs U.S. Nuclear Regulatory Comission Region 1 .c 631 Park Avenue King of Prussia, PA 19406
Reference:
Beaver Valley Power Station, Unit #1 Dockt No. 50-334, License DRP-66 -
Unit I/II Difference Analysis
Dear Mr. Keller:
Please find enclosed the Beaver Valley Unit One-Two Difference Analysis ,
for your review. This is being submitted in accordance with NUREG 1021, ES-106 (Administration of Examinations at Multi Unit Power Stations).
This Difference Analysis addresses Sections C.1, 2, 3 and 4 of ES-106.
Section C.5 (Operational Characteristics) will be forwarded as it becomes available from the N.S.S.S. vendor.
Also enclosed is a copy of the Cross Training Program description.
It is the intent of Duquesne Light Company to requesi a waiver as stated in ES-106, Section G, for the theory section of the written exami-nation and the operating exam. This will be based on the fact that all candidates will already hold a license on Unit I and have operational experience.
Please address any questions or requests for further information to Mr. T. W. Burns of our Training Section. . .
Very truly yours, h
N.J. 'are As f/pce Presi ent iluclear Group O
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Mr. Robert Keller ._ .
June 13,1985 Page 2 bec: J. D. Sieber w/o attachment T. D. Jones W. S. Lacey K. D. Grada E. F. Kurtz "
T. W. Burns w/ attachment T. E. Kuhar .
G. L. Beatty "
T. P. Noonan F(
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-j Unit I/II Cross Training Program Description .. .
Purpose Unit II, Cross Training is provided to prepare licensed Beaver Valley Power Station Unit I Operators for dual licensing on Beaver Valley Units I/II. Train-ing is provided to familiarize operating personnel with (1) Unit II systems and components and differences with the Unit I systems, (2) the proper and approved method for operatir.g these Unit II systems and components by use of Normal Oper-ating Procedures, (3) reactor and plant controls, and station parameters to the extent that operating personnel may take prc-mpt and cc.crect action in the event -
of an unusual occurrence or emergency, and (4) use of Unit II Abnormal and Emer-gency Procedures.
Personnel to be Trained Designated personnel that are licensed on Unit I and required to hold a Unit I/II dual .icense. Reactor Operatort and Senior Operators are provided the neces-sary training in ord'er to dual license.
Scope of Training The Unit II Cross Training Program is approximately eight months in length and includes Unit II System Difference Training, Procedure Training, Simulator Training and License Review Series.
This projected training. time will be appropriately adjusted depending on the examination that will be administered to candidates as detennined by Region 1.
(i.e. if a waiver is granted on theory for the written portion of the examination . <
and the operational portion of the examination due to the candidates being al-ready licensed and experienced, the referenced theory review and simulator train-ing will be deleted).
}
I Training Outlir.e and Schedule - -
Unit II System Difference Training The fifteen week System Difference Training Program for the Cross Training
, Car.didate is based on the differences between Unit I and Unit II systems. The student who is already knowledgeable of the Unit I systems is taught the differ-ences, such that he/she may become qualified on the associated Unit II system.
For this portion of the Training Program an approved lesson plan is utilized which has been developed specifically to explain these differences (example at-tached). A copy of the Unit I/II Difference Analysis is also provided to each
~*
student during this phase.
In addition to classroom instruction on each of the selected systems, the student is given ample study time and time to trace out the respective systems at Unit II. Systems with limited differences may be covered by study packages provided to the student with an instructor available for questions and answers.
Plant Layout The student is given several weeks of in-plant familtarization at the Beaver Valley Power Station Unit II.
Several days are orovided at the beginning of the System Difference training for the initial Unit II exposure and familiarization. This portion of the training consists of guided tours by qualified instructors and time for students to tour on an individual basis. Three weeks are scheduled at the end of the classroom par-tion for in-plant training and familiarization. During this part of the in-plant i familiarization, the student is given a checklist which is a detailed list of major equipment and components which he/she is required to locate and sign off on. This <
completed checklist is part of the system checkout process.
Trainees review and study plant system differences and complete system check-outs by participating in system oriented oral and/or written examinations along with the component checklist described above.
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I Procedures / Technical Specifications Training , .
The Procedures Training will cover Normal Operating Procedures (Startup and Shutdown), Emergency Procedures and Abnormal Procedures. Again, this phase of the training program will stress the differences between Unit I and Unit II since the station will be operated via the'use of approved procedures.
Technical Specifications will also be covered during this phase.
License Review Series This training will consist of a review of major safety related system differences, instrumentation and control functions, administrative procedures -
including Technical Specifications and various areas of related theory. This program will be based on the results of a prereview series examination and the type of examination to be administered by Region I.
Simulator Training A Simulator Training program consisting of a minimum of 5 days (30 Simula-tar Pours) has been designed to ensure all candidates applying for dual licenses receive simulator training and practice on all categories of control manipulations specified in NUREG 0737. The program is intended for personnel currently holding R.0. or S.R.O. licenses on Beaver Valley Unit I. (This program will not be com-pleted if it is determined by Region I that an operational exam can be waivered due to existing experience of the candidate).
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Course Hours Ron Ferrie 4/1/84
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2-I.P-SOS-39.1 Lassen Plan 3a. (Seg" = " *7 I 1)
.m 0o Manual Chapter 39.
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Handouts Attached. .
I Inz: odsu:=1an: ,
- 1. ,~.a: ..
To instruct students on the function and coeration of the 125 VDC 5'vstem.
- 2. Motivation: (Discuss hcw you plan to motivaca scudencs)
Ihportance of the 125 VDC System to the safe operation of the plant.
(Lis: deU".# on.*" e Sectica I)
- 3. General Cut 11sa:
Battery chargers, batteries, switchgear, switchboards, distribution panels, tech. specs., O.S.T.
- 4. . .Ganeral S:=da== G8als: (Lis deca 11ed scudant objectives Sec 1.m. I-) _
- 1) Know the function of the system 4) Discuss tech. scecs.
- 2) Draw the system from memory 5) Discuss system coeration
- 3) Discuss major components 6) Location
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f DUQUESNE LIGHT COMPANT Nuclear Division Nuclear Support Services Depart:nent APPROVAL SHEET - LESSON PLAN AND TEIT REVISIONS Document
Title:
2-LP-S05-39.1 Rev. Subjects Revised Revised Aceroval No. (3rief D<tscription) by Signature Date
,,_Lt3M_ </ ,1, ;~
l 2-LP-SQS-39.1 Pgs. 2,3,5 ////ft/
TP 39.1/39.2 ja,g Annunciator handouts /#7 tocation che-k 14,e u na noir <
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2-LP-SQS-39.1 125 VDC STUDENT OBJECTIVES Af ter this presentation, the student will be able to:
- 1. State the functions of the 125 VDC System.
- 2. Draw from memory a single line diagram of the system including all major components.
- 3. Discuss the following for the major components: ,
I
- a. function
- b. operation
- c. control location i
- d. power supplies 1
- e. ratings
- 4. Discuss the Technical Specifications related to the 125 VDC System.
- 5. Explain both normal and abnormal system operation.
- 6. Demonstrate the ability to locate all system components, controls, and indication.
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2-LP-SOS-39.1 General Outline .
b I. Function of System J
II. General System Description III. Major Components A. Battery Chargers
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- 3. Batteries C. Locations D. Ventilation E. Switchgear i
F. Switchboards and Distribution Panels I
IV. Annunciators V. Tech Specs VI. OST's VII. - Incident Reports I
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I.asson Plan CuW e Instructor Nocas and lei.
I. Function of System - The 125 VDC System supplies power for the following: protection circuits, control cir-cuits, switchgear, local annunciators, vital bus and cssential bus inverters, emergency lights, selected solenoid valves, and operation of turbine-generator e=ergency auxiliaries and emergency diesel generator field flash, and starting circuits.
II. General System Description A. Begin with general description of the flowpath for Differences - batteries 3,4 let a typical battery (TP 39.1), no loads other than inverters '
batteries 5,6 are powered by ._
B. Then using TP 39.2 show the general layout of the essential, not emergency bus, r entire system. have loads which can be powered either battery. Unit 1 has en1 III. Major Components 5 batteries.
A. Battery Chargers
- 1. 5 Power Conversions Products, Inc. battery
-chargers for batteries 1, 2, 5, 6 and a spare.
- 2. 2 Elgar' RECTIFIER / CHARGERS for batteries 3' and 4 (CHARGER / INVERTERS).
- 3. Spare battery charger is located in the Unit I has no spare battery service building el. 730'. charger.
- a. When in use, the spare charger will be bolted in place and plugged into the AC and DC heavy duty switch receptacles located near the equipment to be replaced.
- b. The spare is a full replacement for chargers 1 or 2. When used with batterien 3, 4, 5 or 6, it serves only as a charger since its output capacity is less than
- what would be required to carry the load plus charge the batteries. ,
4 Power Supplies Charger 1 - MCC-2-E5 Unit 1 chargers are powered by Charger 2 - MCC-2-E6 MCCl-E9 and E10.
Charger 3 - MCC-2-E5 Charger 4 - MCC-2-E6 Charger 5 - MCC-2-23 ) powered by Charger 6 - MCC-2-26 ) black diesel
'N Pega 2 of 6 Instructor's Loccon Plcn 2-LP-SQS-39.1 Unit 1 - Unit 2 Differenes:
Lesson Plan Outline Instructor Notes and Refe. uc
- 5. Description of how charger works may be included here (instructor's discretion).
- 6. Indications or Switches
- a. Chargers are equipped with DC voltmeter, m==*ter, input and output circuit breakers, 2 output voltage theostats Unit 1 - all chargers have DC (float and equalize charge), and a 0-24 voltmeters and output circuit hour timer (drawing). breakers.
- b. Charger / inverters are similarly equipped but do not have a DC voltmeter or output e
circuit breaker (wired directly into inverter) (drawing).
B. Batteries
- 1. Description - Batteries 1 thru 4 have 60 cells connected in series. Batteries 5 and 6 have 2 sets of 60 series cells connected in parallel.
- 2. Capacities - Battery capacities are measured, in ampere-hodrs, based on an 8-hour current rating, so the rating is the current the battery can delivery for a period of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- a. Battery 1 - 1345 Ampere-hours
@ 5 hr. discharge rate 2 - 1345 Ampere-hours
@ 5 hr. discharge rate Exide 3 - 860 Ampere-hours
@ 5 hr. discharge rate 4 - 860 A= pere-hours
@ 5 hr. discharge rate 5 - 2400 Ampere-hours
@ 8 hr. discharge rate Gould for both parallel batteries 6 - Same as' Battery #5
- b. Instructor should explain battery discharge curves and go through an example.
O
' S Pcgo 3 of 6 Instructcr'o Lcsscn Plan Unit 1 - Unit 2 Differpnc
~
,, 2-LP-SQS-39.1 Lesson Plan Outline Instructot Notes and Reft. :.
C. Locations
- 1. Each battery is located in its own room.
- a. Battery rooms 1 and 3 - service building el. 730' west end against n. vall.
- b. Battery rooms 2 and 4 - service building el. 730' east end against n. vall.
- c. Battery room 5 - service building el.
760' northwest corner.
- d. Battery room 6 - turbine building el.
752' east side against s. wall.
- 2. Battery chargers are located outside respective battery rooms as are the switchgear for that battery. L ' 'f i " '
- 3. Distribution panels (receive power from the switchboards and supply power through Unit 1 only has 7 distributier independent circuits to small DC loads), panels located in control roca
. or near/in relay room.
j PNL-DC2 control bldg. el. 708' 02 - control bldg. el. 707' l 03 - control bldg. el. 707' 04 - aux. bldg. el. 755' 05 - aux. bldg. el. 755' 06 - service b1dg. el. 730' Unit 1 - diesel sequences are 07 - service bldg. el. 730' powered from VITRUS 1 and 2.
08 - service bldg. el. 760' Unit 2 - diesel sequences are 09 - turbine bldg. el. 730' powered from DIST PNL-06 and 07 10 - main. sem. viv. area el. 735' whicharepoweredfrombatterief 11 - chl. vault & rod cont. area 1 and 2.
el. 735' 12 - 760' n.w. service bldg.
13.- 735' turb. bldg. v. wall 14 - 760' n.e. service bldg.
15 - 760' rod control cable vault '
16 - 760' rod control cable vault p D. Ventilation
- 1. Battery Rooms 2-1 thru 5 are ventilated by FN216A and B to preclude an explosive hydrogen buildup and remove any excessive heat.
- a. Located above battery room 2-5.
i s
Inctructor's Leccon Plan Pega 4 of 6 t 2-LP-SQS-39.1 -
Unit 1 - Unit 2 Diffcre_nc Lesson Plan Outline Instructor Notes and Refc a
- b. Controlled from BSP STOP/AUT0/ START.
AUTO starts on loss of DP across duty fan.
- c. Powered by MCC-2-E13, 14.
- d. 6360 CFM (100% capacity) each.
- 2. Battery Room 2-6 is ventilated by FN271.
- a. Located on the roof of battery room 2-6.
- b. Locally controlled STOP/ START. ,
- c. Powered by MCC-2-1.
- d. 2000 CFM.
- 3. Annunciators .
,a . Battery Room - Air Flow Lov.
b Battery Room Exhaust Fan Auto-Start /
Auto-Stop (216A and B only). .
E. Switchgear - Each of the 6 switchgear assemblies provide a rigid housing for the battery output breaker, instrumentation panel and an instrumenta-tion compartment. Switchgear 5 and 6 also house breakers supplying essential bus inverters 5 and 6 and breakers for the air side seal oil pump and emergency turbine bearing oil pump respectively.
Switchgears 1 and 2 have battery charger disconnects located directly behind the switchgear housing.
- 1. Instrumentation Compartment
- 2. Instrumentation Panel (drawing)
- a. Battery AMP meter 150-0-600 amps -
indication of battery output current or charger current to the battery.
. ~
Pcg2 5 of 6 Instructcr's La: son' Plan
( ,
2-LP-SQS-39.1 Unit 1 - Unit 2 Diffe,anci Lesson Plan Outline Instructor Notes and Refc.
- b. DC Volt Meter 0-150V provides indication of battery or charger output voltage according to position of voltmeter selector switch.
i c. DC Volt Meter for ground indication 150-0-150 indicates a ground on either the positive or negative lead on the associated bus.
- d. Battery breaker indicating lights provide indication of battery breaker position. ..
- e. Other indicating lights for breaker Unit 1 - loads such as air ci such as essential bus inverter, air side seal oil pump do not have ext seal pu=p, etc. breakers right in switchgear,
- 3. Battery Breakers
- a. Explain operations of breaker using Co=pletely different type tre drawing including =anual charging and operations, normal operations, and how ~
(Breakers are exactly the na to rack the breakers in and ou~t. as Unit 2 480V breakers]
F. Switchboards and Distribution Panels
- 1. Switchboards - House the breakers for distribution to various loads.
- a. Certain loads on switchboarls 5 and 6
=ay be powerad by either battery 5 or 6 through mechanically interlocked breakers.
- 2. Distribution Panels - Provide distribution to s= aller loads. Each load has 3 single pole breakers with 2 providing a circuit to the load; the third pole of each breaker is connected in series to actuate an alarm if ,
any one breaker trips.
The 2 current-carrying poles are joined by a handle-tie for ease of operation. (See figure ).
e ,
Pcg7 6 of 6 Unit 1 - Unit 2 Diffcrenc7a f
, 2-LP-SQS-39.1 __
Lasson Plan Outline Instructor Notes and Refc2.. ace IV. Annunciators
- 1. DC Distribution Panel Loss of Control DC Unit 1 - has 7 separate alarms, (Al-1A) one for each distribution panel.
- a. Common alarm with computer printout telling which of the 1G panels is affected.
- 2. 125 VDC Bus 2-( ) Trouble (AS-9A) Unit 1 - has separate alarms for battery breakers 0.C., low volta
- a. Computer printout telling if: and charger failure.
- 1. BAT BKR 0.C.
ii. VOLTAGE (LOW) 111. CHARGER
- 3. 125 VDC SWBD EKE TRIP ( AS-10A) Unit 1 - has separate alarms for specific breaker tripping.
- a. Computer printout listing specific breaker 2- 1, 2- 2, 2- 5 o r 2- 6 .
V. Tech Specs
- 1. Later.
VI. OST's
- 1. Later VII. Incident Reports
~
- 1. Review any recent incidents.
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Filsura 0.7 DUQUESEE LIG C CCMPANT ,
m,t ..,- Division
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T;.4 4,. M.anual .
LISSON P W
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45 minnea.
'u..cene v..ne, Course Ecurs Couzza .
August 16, 1984 -
A. Lee m
pW
) H 2 r> nnn a 9 Lasaca Plan No. (Seg"=a"' C '7 Iccm 1)
/ Ayy .,4 37: .
_]
Inferencas In Be Quotadt. OM chaeter 6. Unit 2. OM chaeter 6 Unt* 1 i
l .
Icems. Issuadi '(iet-e3= copy of all passauts, quiz =as, ecc.)
t .
All lesson olant drawines .
T.st= **d = : .
1.
Purpose:
To inform the student o'f the differences between the Reactor of Fa4 e 7 /?
j
. k Macivac1=n: (Discuss hcw you plan es ascivate scudents)
,-a <ns, n.,er,*4n- es avec n'
' Infor-irion rec.,4- a cor tvi,4r 2 14c e.,
- 3. General C"-t 'a=: (T.ist durcailed' ou,c11sa Sec dcn 'I)
I. Introduction II 2eactor Vessel Off#erence Reports III. Operationsl Differences IV Tech Soecs V Incident (Lisc decalled scudant objec*'_ves Seccion II) .
- 4. . . General Scudent Geils:
-uo v-*~ ' m-A m , - . . s n. ~ vf11 he nhie en erneo e ', e a t *
Unit 2 Reactor Vessel' and h at Vent Svstem
3 SECTION If ,
Reactor Vessel ,, ,
2LP-2QS-6.2 STUDENT OBJECTIVES At the completion of this lecture, the student should be able to:
- 1) Explain and locate major control and protection instrumentation and controls associated with the reactor vessel.
- 2) State the cbjectives of the procedures associated with the reactor vessel and reactor head vent system.
- 3) Explain the bases of any precautions or limitations pertaining to the reactor vessel and reactor head vent system. .c
- 4) Repeat from memory all Technical Specifications and associated action statements where action is required within one hour and discuss associated basis.
- 5) Be able to list differences of the above items with the UNIT 1 system.
- 6) Point out differences between the UNIT 1 and UNIT 2 reactor vessel and internals with an illustration of the UNIT 2 reactor vessel.
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~
e SECTION I Reactor Vessel - Unit 1/2 Differences 2LP-SQS-6.2 GENERAL OUTLINE I. INTRODUCTION TO UNIT 2 REACTOR VESSEL II. REACTOR VESSEL DIFFERENCES WITH RESPECT .e TO UNIT 1 A. O Rings B. d #Jdre / # ,/s C. ThermakShield D. Level Indication -
. E. Reactor Vessel Flange Leakoff *
- 1. Function
- 2. Instrumentation and Control F. Reactor Vessel Head Vent System
- 1. Function
- 2. Instrumentation and Control III.0PERATIONAL DIFFERENCES WITH RESPECT TO UNIT 1 A. Procedures B. Precaution and Limitations IV. TECHNICAL SPECIFICATION (DIFFERENCES) .
V. INCIDENT REP 0ftTS 2
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F.assc Y --' Cu~ a b ,,,,_c::: s7a:1, a 5 7,.
2LP-SQS -ti . 2 I. INTRCDUCTION TO UNIT 2 REAC T)R VESSEL Reactor Vessel FIG. 1 (2RCS*REV21]
The vessel is a vertical cylindrical steel vessel with a hemispherical ,
bottom head and a flanged and gasket hemicpherical upper head.
II. REACTCR VESSEL DIFFERENCES '4ITH RESPECT NOTE:Unless specified, TO UNIT 1 all information concerning the Unit 1 and 2 reactor vessel is the same.
A. O Rings Two hollow silver plated-Nrcr-Fe Difference alloy "0" rings form the pressure tight "0" rings are made seal of the vessel flange at the closure out of stainless steel head. . in Unit 1.
- 3. 6dn/ 4 /s
(%/r s / A'Js pg ser/e cuf o;f Ditforence MrLvsm awa e < e oS /Je /or;#4 p is , g;,f,,)g4 ,,,,
humode%e assock /e/ uss# (b-a. . mads ee/of 97,S,wa4 H:5 dwer -d s: da% e C. Thermal Shield ,
FIG. O The thermal shield is divided into Difference four panels. -~'hese are four radial Unit 1 thermal shield
- shaped panels located between the is one cylindrical piece, vessel wall and the core barrel at The Unit 2 design is the core elevation. Separation an i=provement that .
~
between the shield and the barrel results in a more uniform is maintained by spacer blocks flux pattern while using blocks welded to the shield and less material. The core barrel blocks that are bolted The vessel 's not together. exposed to my higner flux with this improvement.
l Page 3
I.::sc ..c n 's T.asrcu' Plan T.assen ?' -- Cu ' ' a T. .s -- c:;: !Tc ns a=:i i c-2LP-SQS-6.2 D. Level Indication FIG. 3 2RCS*LG102 is specifically used for Difference vessel indication during refueling Unit I uses a drain located on loop 23 hot leg. (730' connection on the containment) 2RCS*LT102 will supply pressurizer for input to a remote indication in reactor vessel level the control room. during refueling and when the reactor coolant INDICATION RANGE DESCRIPTION system is drained down to mid span by attaching 2RCS-LR102 0-36" Hot Leg C Level a tygon hose.
2RCS-LIl02 0-36" Hot Leg C Level 14S -/.4 /0/ 4-JFY w gjg, c xeree Swd NOTE: Inadequate informa-tion available on Unit 2 RVLIS E. Reactor Vessel Flange Leakoff Valve [2RCS*A0V5441
- 1. Function .
The reactor vessel flange leakoff Difference valve is controlled from the None benchboard - Section A. Switch positions are OPEN-CI4SE with red (open) and green (shut) indicating lights used to isolate leaking 0 rings.
- 2. Instrumentation and Control OPEN CLOSE 2RCS*A0V544 . 1. In "0 PEN" 1. In "CLOSE" Control location ,
23-A4 Initial NSA*0 PEN Power Supply:
PNL*DC2-01 (SMuvC/s/MNio 4*wMr)
Page 4
' '.:sc:..c:: d 3 T.asacn'?? m T.assen ?'-~ Cu"'d e s c:=;- notas a=:i7,c 2LP-SQS-6.2 INDICATION RANGE DESCRIPTION 2RCS*TI401 50-300*F Reactor Flange VBA8 leakoff temp.
high ANNUNCIATOR INPUT SETPOINT DESCRIPTION 2RCS*TYH401 (Later) REACTOR FLANGE LEAK 0FF TEMP.
HIGH.
(Later)
F. Reactor Vessel Head Vent System
- 1. Function FIG. 4, 5 The reactor vessel head vent system Difference is designed to remove non- -
The Unit 1 reactor condensible gasas and provide coolant gas vent letdown capability from the system takes suction reactor coolant system via from two points.
remote manual operations from A. The reactor vessel.
the control room. The system B. The pressurizer.
discharges to the Pressurizar Relief Tank [2RCS-TK22]. The It discharges to:
reactor vessel head vent A. Pressurizer system is designed to vent relief tank.
a volume of hydrogen at system B. Containment.
design pressure and temperature approxi=ately equivalent to one half of the reactor coolant system in one hour. The reactor vessel head vent system also provides venting capability during reactor coolant system fill and venting procedures .
The system consists of four one- Difference inch open/close solenoid- The Unit I reactor operated isolation valves coolant gas vent connected to the 1 inch reactor system has six valves, vessel vent pipe, which is two associated with located near the center of the each suction point reactor vessel head. The system and one associated with two valves in series mini- with each discharge Page 5
~
s hs - c .7.'s Lassen* P' "
T.assen ?' m Cu a v e =; gota3 a=:i 7,g 2LP-SQS-6.2 mi es the possibility of reactor point. The valves are coolant pressure boundary leakage. administratively con-Isolation valves (2RCS*SOV201A trolled such that.
and *SOV201A] in one flow path only one suction and are powered from (125VDCPNL*DC2-11-24] one discharge point and valve (2RCS*SOV200B and *SOV201B] can be used at any in the second flow path are powered one time.
from (125VDC PNL*DC2-10-18]
Location - (Later) Refer to 11241-LSK-9 A(B)
- 2. Instrumentation and Control OPEN CLOSE FIG. 4, 6, 7 Reactor Vessel 1. In "0 PEN" 2. In "CLOSE" Difference letdown isolation SOV-RC-102A(B) valves will open provided
[2RCS*SOV200A(B)] SOV-RC-103A(B)
[2RCS*SOV201A(B)] are closed. These are Control location: administrative controls.
(Later)
Position: SOV-RC-103A(B)
OPEN-CLOSE . . will open provided Initial NSA+Close SOV-RC-102A(B)
Power Supply are closed. These are PNL*PC2-11-24 administrative controls.
(10-18) SOV-RC-104 will open provided 50V-RC-105 is closed. This is a administrative control.
SOV-RC-105 will open provided S0V-RC-104 is closed. This is a administrative control.
[2RCS*HCV250A] Position to setpoint Difference
[2RCS*HCV250B] Corresponding to controller. No regulating Control Location: (Later) valve in the
. (Later) Unit 1 over-pressure relief system.
Page 6
) T.ssL ccr's LaCacn"Pl.an
?.asson ?' " Cu '* a T %. c=r ! Tot:ss and .
2LP-SQS-6.2 A pressure guage and annunciator is also associated with leakage of SOV-RC-iO2A(B) and SOV-RC-103A(B) in Unit 1 INDICATION RANGE DESCRIPTION leMt.
2RCS*FG200 (Later) Reactor head ,_
vent flow III. OPERATIONAL DIFFERENCES WITH RESPECT TO UNIT 1 A) Procedures (Later)
B) Precautions and Limitations Refer to 2.6.2 V TECHNICAL SPECIFICATIONS DIFFERENCES (Later)
V INCIDENT REPORTS (N/A)
. Page 7
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2LP-SQS-6.2 D. Level Indication FIG. 3 2RCS*LG102 is specifical.1.y used for Difference vessel indication during refueling Uc.it I uses a drain located on loop 23 hot leg. (730' connection on the containment) 2RCS*LT102 will supply pressurizer for input to a remote indication in reactor vessel level the control room. during refueling and when the reactor coolant INDICATION RANGE DESCRIPTION system is drained down ._
to mid span by attaching 2RCS-LR102 0-36" Hot Leg C Level a tygon hose.
8RCS-LIl02 0-36" Hot Leg C Level NOTE. Inadequate informa-tion available on Unit 2 RVLIS E. Reactor Vessel Flange Leakoff Valve [2RCS*A0V5441
- 1. Function The reactor vessel flange leakoff Difference valve is controlled from the None benchboard - Section A. Switch positions are OPEN-CLOSE with rad (open) and green (shut) indicating lights used to isolate leaking 0 rings.
, s ,f ga
- 2. Instrumentation and Control DLJ b hh $
OPEN CLOSE A
2RC'S*A0V544 1. In "CPEN" 1. In "CLOSE" Control location .
BB-A4 Initial NSA1 PEN / #g Power Supply: /
PNL*DC2-01 Page 4
SECTION I ,
Reactor Vessel - Unit 1/2 Differences 2LP-SQS-6.2 GENERAL OCTTLINE I. INTRODUCTION TO UNIT 2 REACTOR VESSEL II. REACTOR VESSEL DIFFERENCES WITH RESPECT .c TO UNIT 1 A. O Rings B. Claddina C. Thermal Shield D. Level Indication E. Reactor Vessel Flange Leakoff -
- 1. Function
- 2. Instrumentation and Control i F. Reactor Vessel Head Vent System
- 1. Function
- 2. Instrumentation and Control III.0PERATI'ONAL DIFFERENCES WITH RESPECT TO UNIT 1 A'. Procedures B. Precaution and Limitations IV. TECHNICAL SPECIFICATION (DIFFERENCES) ,
t V. INCIDENT REPORTS i
4
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Lasscr.P' m Cu e -, :::::: ro:23 23 7,, ,7 2LP-SQS-6.2 I. I.NTRODUCTION TO UNIT 2 REACTOR VESSEL Reactor Vessel FIG. 1
[2RCS*REV21)
The vessel is a vertical cylindrical steel vessel with a hemispherical bottom head and a flanged and gasket hemispherical upper head.
II. REACTOR VESSEL DIFFERENCES WITH RESl__T NOTE:Unless specified, ,,
TO UNIT 1 all information concerning the Unit 1 and 2 reactor vessel is the same.
A. 9 Kings Two hollow silver plated-NrCr-Fe Difference alloy "0" rings form the pressure tight "0" rings are made seal of the vessel flande at the closure out of stainless stael head. -
in Unit 1.
B. Cladding All carbon steel surfaces that are in Difference contact with the reactor coolant are clad All carbon steel cladding with S/32 inch minimum stainless steel to with 1/8 inch (4/32")
inprove corrosion protection. minimum stainless steel in Unit 1 C. Thermal Shield FIG. 2 The thermal shield is divided into Difference four panels. These are four radial Unit 1 thermal shield shaped panel.n loc.ited between the is one cylindrical piece.
. vessel well and the core barrel at The Unit 2 design is the core elevation. Separation an improvement that between the shield and t,he barrel results in a more uniform is maintained by spacar blocks flux pattern while using blocks welded to the shield and less material. The cote barrel blocks that are bolted The vessel is not together. exposed to any higher flux 1 with this improvement.
1 i Page 3
~
.a.s.s- ct:f s !.as:on' Plan Lassen 712:1 Cu-' d a ?-*:::c::: To:2s a=d L_
- 2LP-SQS-6.2 A pressure guage and annunciator is also associated with leakage of SOV-RC-102A(B) and SOV-RC-103A(B) in Unit 1 INDICATION RANGE DESCRIPTION 2RCS*FG200 (Later) Reactor head ,,
, vent flow III. OPERATIONAL DIFFERENCES WITH RESPECT TO UNIT 1 A) Procedures (Later)
B) Precautions and Limitations Refer to 2.6.2 V TECHNICAL SPECIFICATIONS DIFFERENCES (Later)
V INCIDE.Vr REPORTS (N/A) e 9
Page 7