|
|---|
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] |
Text
--
O e
. Shippingport, PA 15077-0004 n Yh.e esWent Fax 2 -8 Nuclear Services Nuclear Power Division U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Ststion, Unit No. I and No. 2 BV-1 Docket Na 40-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Emergency Response Data System (ERDS) ]
In accordance with the requirements of 10 CFR Part 50, Appendix E, Section ,
VI.3.a and NUREG-1394, Revision 1, Section 3.6, " Administrative Implementation l Requirements," the enclosed Data Point Library (DPL) changes are being submitted. !
Seven(7) Beaver Valley Power Station (BVPS) Unit No. I DPLs have undergone a !
change in the radiation monitor alarm setpoints so that the setpoint coincides with a (
major or minor scale division. Four (4) BVPS Unit No. 2 DPLs have undergone a change in the plant specific point description in order to match the Plant Safety Monitoring System descriptions of points with the same functions. These changes are currently in effect on the BVPS plant computers which provide data to the ERDS computer.
If you have any questions concerning the DPL changes, please contact Mr. J. Arias, !
Director, Safety & Licensing Department, (412) 393-5203. l 4
1 Sincerely, I Sushil C. Jain I !
t :
Mr. D. M. Kern, Sr. Resident Inspector c:
Mr. H. J. Miller, NRC Region I Administrator b9yb Mr. D. S. Brinkman, Sr. Project Manager i Mr. J. R. Jolicoeur, USNRC Incident Response Branch Mr. R. R. Keimig, NRC Region I, Emergency Preparedness DEllVERING Mr. P. D. Kaufman, NRC Region I, Emergency Preparedness WOO 11 Eue,s, 9704070116 970403 3 IEEEEhh,E.@
PDR ADOCK 05000334 F PDR ,
7 e.
BEAVER VALLEY POWER STATION ERD 3 DATA POINT LIBRARY DV1 ERDS INPt7T Dates 03/06/97 j React.or Unite BV1 Data Feeder IPC NRC ERDS Parameters EXTRAI8
_. Point ids YO"105A Plant Spec Point Desc.i COMP COOLING /RECIRC SPRAY HX RW i
Generic /Cond Dese,t RAD!OACTIVITY OF RELEASED LIQUID r
Analog / Digitals A Engr Units / Dig States: CPM Engr Units Conversions N/A r
Minimum Instr Range 10 l
Maxio n Instr Range: 1E6 9
Zero Point
Reference:
N/A Reference Point Notest N/A PROC or SENS: S Number Of Sensors: 1 How Processed: N/A Sensor Locations: SEE UNIQUE SYSTEM DF,SCitIPTION FIELD Alarm / Trip Set Points: HI AIJt a 1.00E4 CPM NI Detector Power Supply Cut-of f Power Level: N/A NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: LOW Temperature Compensation For DP Transmitters: N Level Reference Legt N/A Unique System Dese. RM-1RW-100 SAMPLES FOR ACTIVITY (CO-60 & CS-137) AT THE DISCHARGE OF THE REACTOR COMPONENT COOLING WATER HEAT EXCHANGERS. FOLLOWING A CIB SIGNAL THE HHSI PUMP OIL COOLER AND THE RECIRC SPRAY HEAT EXCHANGER DISCHARGE IS ALSO MONITORED. HIGH ACTIVITY IS INDICATIVE OF A HEAT EXCHANGER LEAK. A GAMMA SCINTILLATION DETECTOR MONITORS THE COMBINED RIVER WATER DISCHARGE MANIFOLD DOWNSTREAM OF THE REACTOR PLANT COMPONENT COOLING WATER /RECIRC SPRAY HEAT EXCHANGERS.
OP MANUAL CHAPTER 43., RM-430-3 s
_.s. - _ ._.
1 J
DEAVER VALLEY POWER STATION ERDS DATA POINT LIBRARY e
BV1 ERDS INPtTT Datee 03/06/97 5
.' Reactor Unit:. BV1.
J Data Feeder IPC NRC ERDS Parameters EXTRA 19 t
Point ids YO735A ,
Plant Spec Point Desc.: REACTOR CONTAINMENT L/R Generic /Cond Desc.: RADIATION LEVEL IN CONTAINMENT Analog / Digital: A i
Engr Urtits/ Dig Statess. MR/HR Eng'r Units Conversions N/A ,
Minimum Instr Range 0.1 .
Maximum Instr Range 10000 Eero Point
Reference:
N/A Reference Point Notes: N/A i
PROC or SENS: S Number Of Sensores 1 How Processeds. N/A Sensor locatione s SEE UNIQUE SYSTEM DESCRIPTION FIELD Alarm / Trip Set Points: HI AIN e 20.0 MR/HR J
NI Detector Power Supply Cut-off Power Levels N/A NI Detector Power Supply Turn-on Power Levelt N/A
' Instrument Failure Moder Iow
'l Temperature Compensation For DP Transmitterna N I
Level Reference Lega N/A Unique System Dese.: RM-1RM-202 MONITORS THE RADIATION LEVEL INSIDE CONTAINME:rt AND NARNS PERSONNEL OF AN INCRRASE IN THE RADIATION LEVEL. A GEIOER-MUM.fRR DETECTOR MONITORS RADIATION LEVEL INSIDE CONTAIh N
'OF THE CRANE WALL OPPOSITE THE PERSONNEL ACCESS. OP MANUAL CHAPTER o !
i
- . < 3 l
.r '
S, p ' )
)
a BEAVER VALLEY POWER STATIOri EADS DATA POINT LIBRARY BV1 ERDS INPUT Dat e r* 03/06/97 Reactor IJnit s BV1 Data Feeder IPC NRC ERDS Parameters EFF-LIQ-RAD 1 Polbt ID: R0030A' Plant Spec Point Desc. LIQUID WASTE EFFLUENT Generic /Cond Desc,i RADIOACTIVITY OF RELEASED LIQUID Analog / Digital: A
' Engr Units / Dig States: CPM Engr Units Conversion: N/A Minimum Instr Range: 10 Maximum Instr Range: IE6 Zero Point
Reference:
N/A Reference Point Notest N/A PROC or SENS: S Number Of Sensors: 1 How Processed: N/A Sensor Locationsi SEE UNIQUE SYSTEM DESCRIPTION FIELD Alarm / Trip Set Pointsi HI ALM e 2.00E5 CPM /LO ALM e -1600 CPM NI Detector Power Supply Cut-off Power Level: N/A NI Detector Power Supply Turn-on Power Leveli N/A Instrument Failure Mode: LOW Temperature Compensation For DP Transmitterst N Level Reference Leg N/A Unique System Desc.: RM-1LW-104 MONITORS THE ACTIVITY (CO-60 & CS-137)'OF ANY RADIOACTIVE LIQUID WASTE DISCHARGEO FROM THE STATION. A HIGH-HIGH ACTIVITY AUTOMATICALLY TERMINATES FLOW BY CLOSING THE DISCHARGB LI.NE ISOLATION VALVE.". A GAMMA SCINTILLATION DETECTOR MONITORS THE ACTIVITY OF RADIOACTIVE LIQUID WASTE DISCHARGED DOWNSTREAM OF THE LAST POINT OF RADIOACTIVE EFFLUENT ADDITION TO THE DISCHARGE HEADER. OP MANUAL CHAPTER 43, RM-417-1
.. .. [
BEAVER VALLEY POWER STATIOG1 ERDS DATA POI!ff LIBRARY f BV1 ERDS INPUT Date r . 03/06/97 >
Reactor Uniti BV1 P
)
Dat.a Feeder IPC
[
' NRC ERDS Parameter ' SG-BD-RAD-1A t
, Point ID: R0034A Plant Spec Point Desc.i STEAM GENERATOR BLOW XniN Q
Generic /Cond Desc.s S1M GEN A/B/C BLOWDOWN RAD LEVEL ;
Analog /Digitalt A ,
Engr Units / Dig States:- CPM Engr Units Conversioni N/A Minimum Instr Ranget 10 s Maximum Instr Rangen 1E6 Eero Point Reference N/A Reference Point Notes: N/A PROC or SENS: S Number Of Sensors: 1 How Processed: N/A i
Sensor Locations SEE UNIQUE SYSTEM DESCRIPTION FIELD Alarm / Trip Set Points: Hi ALM e 1000 CPM /LO AIN e -100 CPM l
N1 Detector Power Supply Cut-of f Power 1.evel N/A l l
1 NI Detector Power Supply Turn-on Power Levels N/A !
. Instrument Failure Mode: LOW l
Tefnperature Compensation For DP Transmitters: N j l
Level Reference Leg N/A Unique System Desc.t RM 1BD-100 MONITORS THE BLOWDOWN DISCHARGED FROM THE BLOWDOWN HEAT EXCHANGER DISCHARGE LINE FOR CO-60 AND CS-137. A HIGH-HIGH ALARM MAY INDICATE A PRIMARY TO SECONDARY LEAK. A GAMMA SCINTILLATOR
' DETECTS ACTIVITY FROM SAMPLES TAKEN AT THE DIbCHARGE OF THE BLOWDOWN DRAIN HEAT EXCHANGER. OP MANUAL OIAPTER a3.
_m
i-BEAVER VALLEY POWER STATIOi# ERDS DATA POINT LIBRARY BV1 ERDS INPtJT IDater 07/22/96 Reactor Unit BV1 i
l0.*a /eeders IPC
- NRC ERDS Parameter: RCS-LTD-RAD 1 Point ID: R0036A Plant Spec Point Desc.: RX COOLANT. LETDOWN HI RANGE
' Generic /Cond Desc.: RAD LEVEL OF RCS LETDOWN LINE Analog / Digitals -A Engr Units / Dig States: CPM Engr IJnits Conversion N/A Minimum Instr Ranges 10
. Maximum Instr Range: 1E6 Eero Point References N/A Reference Point Notes: N/A PROC or SENS: S Number Of Sensors: 1 I
How Processed: N/A Sensor Locatie..s: SEE UNIQUE SYSTEM DESCRIPTION FIELD Alarm / Trip Set. Points: HI AIN e 6.0E5 CPM /LO ALM e -6.4E3 CPM s
NI Detector Power Supply Cut-off Power Level N/A o
HI Detector Power Supply Turn-on Power Level N/A Instrument Fdilure Mode: LOW
.T3mperature Compensation For DP Transmitters: N e
Level Reference Leg N/A Unique System Desc.: RM-1CH-101A MONITORS THE GROSS ACTIVITY OF TIE REACTOR COOLANT (CO-60 & CS-137) BY DRAWING SAMPLES FROM THE REACTOR COOLANT LETDOWN LINE AND DELAYING THEM TO PERMIT SUFFICIENT DECAY OF THE N 16 ISOTOPE BEFORE THEY PASS BY THE DETEC"f0RS. THIS IS AN INDICATION OF FISSION PRODUCTS PRESENT IN THE REACTOR COOLANT. THIS RADIATION MONITOR PROVIDES THE LOW AND HIGH RANGE INDICATION. A GAMMA SCINTILLATION DETECTOR MONITORS THE GROSS ACTIVITY OF THE REACTOR COOLANT BY DRAWING SAMILES FROM THE RFJLCTOR COOLANT LETDOWN LINE DOWNSTEAM OF THE NON-RECENERATIVE HEAT EXCHANGER. CM 4 3.
___J
6
BEAVER VALLE7 POWER STATION ERDS DATA POINT LIBRARY BVI ERDS INPtTT
- Dater 03/06/97 b
Reactor Unite BV1 Data Fee $er IPC ,
. i NRC ERDS Parameters RCS-LTD-RAD 2 Point ID: R0037A 4
Plant Spec Point Dese.1 RX COOLANT LETDOWN LO RANGE k
[
. Generic /Cond Dese.: ' RAD LEVFL OF RCS LETDOWN LINE {
~
Analog /Digitali- A
- Engr Units / Dig States CPM Engr Units Conversion N/A Minimum Instr Range 10 Maximum Instr Range
- 1E6 Zero Point
Reference:
N/A Referer.ce Point Notes: N/A PROC or SENS: S i
I Number of Sensors -1 '
How Processed: N/A Sensor Locaticns: SEE UNIQUE SYSTEM DESCRIPTION FIELD Alarm / Trip Set Points: HI ALM e 4.0E4 CPM /LO AIN e -6.4E3 CPM l
NI Detector Power Supply Cut-off Power Level: N/A f NI Detector Power Supply Turn-on Power Level N/A j Instrument Failure Mode LOW l Temperature Compensation For DP Transmitters: N i
Level Reference Leg N/A ;
Unique System Desc.: RM 1CH-101B MONITORS THE GROSS ACTIVITY OF THE REACTOR COOI. ANT (CO-60 & CS-137) BY DRAWING SAMFLES FROM THE REACTOR COOLANT LETDOWN LINE AND DELAYING THEM TO PERMIT SUFFICIENT DECAY OF THE N 16 ISOTOPE BEFORE THEY PASS BY THE DETECTORS. THIS IS AN INDICATION OF FISSION PRODUCTS PRESENT IN THE REACTOR COOLANT. T)fIS RADIATION MONITOR PROVIDES THE LOW AND HIGH RANGE INDICATION. A GAMMA SCINTILLATIQN DETECTOR MONI'IVRS THE GROSS ACTIVITY OF THE REACTOR COOLANT BY DRAWING SAMPLES FROM THE REACTOR COOLANT LETDOWN LINE DOWNSTEAM OF THE NON-REGENERATIVE HEAT EXCHANGER. OM 43.
, .1
.t BEAVER VALLET POWER CTATION ERDS DATA POINT'LIERARY BV1 ERDS INPUT-
' Dato p - 03/06/97-Reactor Units BV1 Data Feeders- IPC ,
n NRC ERDG Parameters 'EFF-LIQ-RAD 2 Point ID YO717A Plant Spec Point Desc. LIQUID WASTE CONTAINMENT DN EFF ,
1 Generic /Cond Desc,I RADIOACTIVITY OF RELEASED LIQUID Analog / Digital: A Engr Units / Dig Statesi CPM l Engr Unite Conversion: N/A 4
Minimum Instr Range: 10 Maximum Instr Ranger 1E6 ,
,Zero Point References- N/A ,
Reference Point Notes: N/A PPOC or SENS: S Number Of Sensors: 1 How Processed: N/A l
Sensor Locations: SEE UNIQUE SYSTEM DESCRIPTION FIELD I
Alarm / Trip Set Points: HI ALM e 6.00E5 CPM 41 Detector Power Supply Cut-of f Power Level N/A NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: LOW Temperature Compensation For DP Trar.smitters: N Level Reference Lega N/A Unique System Desc. RM-1LW-116 CONTINU0CSLY MONITORS THE ACTIVITY (CO-60 & CS-137) OF l i
THE EFFLUENT DOWNSTREAM OF THE LIQUID NASTE CONT.*AINATED DRAINF j FILTER. A HIGH-RIGH ACTIVITY h1LL Ai?TOMATICALLY CLOSE THE ISOL. TION VALVES TO TERMINATE FIDW. A GAMMA SCINTILLATION DETECTOR WAITORS THE ACTIVITY OF LIQUID WASTE COh*TAMINATED DRAINS EFFLUENT DOWNSTREAM OF THE CONTAMINATED DRAINS FILTER.-OP 4ANUAL CHAPTER 43, RM-417 1
s t
'.d
'e BEAVER VALLEY POWER STATIG3 ERD 3 DATA POINT LIBRARY BV2 ERDS INPUT Datef 03/06/97 Remetor Unita BV2 Data Feeders ERFCS NRC ERDS Parameterr REAC-VES LV3 Point ids LOO 71A Plant Spec Point Desc.t RVLIS-A FULL RANGE RCS*LIS1311 Generic /Cond Dese, REACTOR VESSEL NATER LEVEL Analog / Digital: A Engr Units / Dig Statesi 4 Er.gr Units Conversions. PSMS RVLIS ALGORITHM i
Minimum Instr Rangen 0 Maximum Instr Range 120 i Eero Point
Reference:
TAF Reference Point Notes: TAF=729'3"(276" FROM BOT RX VESS)=62.5%
PROC or SENS: S Number Of Sensorsi 1 How Processed: PSMS RVLIS ALGORITHM Sensor Locationna SEE UNIQUE SYSTEM DESCRIPTION FIELD l j
i Altrm/ Trip Set Points: N/A I
NI Detector Power Supply Cut-off Power Level N/A NI Detector Power Supply Turn-on Power Leveli N/A l
Instrument Failure Modes In. l I
Temperature Compensation For DP Transmitters: Y I
1 Level Reference Legt, NET Unique System Desc.: CONNECTIONS TO THE RX VES HEAD AND INCORE INSTRUMENTATION TUBE #20 l
AT THE SEAL TABLE ARE THE SENSING POINTS. REFF.RENCE LINE TUBING '
RUNS FROM THESE POINTS TO HIGH VOLUME SENSORS WHICH ISOIATE THE RCS FROM THE REMAINDER OF THE RVLIS TUBING. CAPILLARY TUBING RUNS FROM THE HIGH VOLUME SENSORS THROUGH THE CNTNT WALL TO HYDRAULIC ISOIATORS. RTD'S ARE INSTALLED ON CAPILLIARY LIN*S FOR CNMNT TEMP.
COMPENSATION. PSMS RECEIVES TRANSMITTER OtJTPUT READING IS INVALID IF RCPS ARE RUNNING 2RCS*LT1311 SENSES RX VES LEV BETWEEN THE TOP OF THE RX VES HEAD ELEV 746*6* TO THIMBLE GUIDE TUBE N20 ELEV
i
.s.
- . o EEAVER VALLEY POCER STATION ERDS DATA POINT LIBRARY ,
a'
BV2 ERDS INPUT
~
Datei 03/06/97
~
Reactor Units- ' BV2 Data Feeders ERFCS NRC ERDS Parameters REAC-VES-LV1
?
Point ids .L0072A Plant Spec Point Desc., RVLIS+A DYNAMIC RANGE LIS1312 -
r Generic /Cond Desc.s. REACTOR VESSEL WATER LEVEL Analog / Digital: A
't Engr Units / Dig States: 4 Engr Units Conversions N/A Minimum Instr Range: 0 Maximum Instr Range: 120 Zero Point
Reference:
N/A Reference Point Notes: N/A
- PROC or SENS: S Number Of Sensors: 1 How Processed: PSMS RVLIS ALGORITHM Sensor Locations: SEE UNIQUE SYSTEM DESCRIPTION FIELD i
Alarm / Trip Set Points N/A NI Detector Power Supply Cut-off Power Level: N/A l
NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: LOW 1
i Temperature Compennation For DP Transmitters: Y Level Reference Leg WET Unique System Desc.s. CONNECTIONS TO THE RX VES HEAD AT THE INCORE INSTRUMENTATION TUBES SENSE RX VES CORE AND INTERNAL DP. REFERENCE LINE TUBING RUNS FROM THE INSTRUMENT TUBES TO HIGH VOLUME SENSORS WHICH ISOLATE THE RCS FROM THE REMAINOER OF THE RVLIS TUBINO. CAPILLARY TUBINO RUNS FROM i THE HIGH VOLUME SENSORS THROUGH THE CNTNT WALL 'IV HYDRAULIC ISOLATORS. RTD'S ARE INSTALLED ON CAPILLIARY LINES FOR CNMNT TEMP, COMPENSATION. PSMS RECEIVES TRANSMITTER OUTPUT. READING IS INVALID UNLESS RCPS ARE RUNNING. 2RCS*LT1312 SENSES DP ACROSS RX VES CORE
'AND INTERNALS WHEN ANY RCPS ARE RUNNING. NORMAL DP IS 110-112%
4
J e
BEAVER VALLEY POWER STATIC 3 ERDS DATA POINT LIBRARY BV2 ERDS INPUT Datef 03/06/97
- Reactor Unit BV2 Det.a Feeders. ERFCS
-NRC ERDS Parameters REAC-VES-LV4 Point ID LOO 74A Plant Spec Point Dese, RVLIS B FULL RANGE RCS*LIS1321 Oeneric/Cond Dese.: REACTOR VESSEL WATER LEVEL Analog / Digital: A Engr Units / Dig States %
. Engr Units Conversiont PSMS RVLIS AIDORITHM M.inimum Instr Range: 0 Maximum Instr Range 120 Zero Point
Reference:
TAF Reference Point Notes: TAF=729'3'(276' FROM BOT RX VESS)=62.5%
PROC or SENS: S Number Of Sensors: 1 How Processed: PSMS RVLIS ALGORITHM i
J Sensor Locations: SEE UNIQUE SYSTEM DESCRIPTION FIELD l
Alarm / Trip Set Points: N/A NI Detector Power Supply Cut-off Power Level N/A j
( NI Detector Power Supply Turn-on Power Level: N/A i I
Instrument Failure Mode LOW Temperature Compensation For DP Transmitters: Y Invel Reference Legt WET Unique System Desc.1 CONNECTIONS TO THE RX VES HEAD AND INCORE INSTRUMENTATION TUBE #20 AT THE SEAL TABLE ARE THE SENSINO POINTS. REFERENCE LINE TUBING RUNS FROM THESE POINTS TO HIGH VOLUME SENSORS WHIC58 ISOLATE THE RCS FROM THE REM *INDER OF THE RVLIS TUBING. CAPILLARY TUBING RUNS FROM THE HIGH VOLUME SENSORS THROUGH THE ClfrNT WALL TO HYDRAULIC y ISOLATORS. RTD'S ARE INSTALLED ON CAPILLIARY LINES FOR CNMNT TEMP.
COMPENSATION. PSMS RECCIVES TRANSMITTER OUTPUT. READING IS INVALID IF RCPS ARE RUNNING. 2RCS*LT1321 SENSES RX VES LEV BETWEEN THE TOP OF THE RX VES HEAD ELEV 746'9' TO '1HIMBLE CUIDE TUBE #20 ELEV
i 4
BEAVER t' ALLEY PCCER STATIC ~1 ERDS DATA FOINT LIBRARY
.BV2 ERDS INPUT ,
Date r .- 03/06/97
. Reactor Unita BV2 Data Feeders ERFCS NRC ERDS Parameters REAC-VES-LV2 Point ID: LOO 75A .;
Plant Spec Point Desc.s RVLIS-B DYNAMIC RANGE LIS1322 Generic /Cond Dese.: REACTOR VESSEL WATER. LEVEL Analog / Digital: A Engr Units / Dig States: - %
Engr Units Conversion N/A ]
l Minimum Instr Ranget 0 l Maximum Instr Ranger 120 l l
Zero Point Reference N/A 1
Reference Point Notes: N/A PROC or SENS: S Number Of Sensors: 1 How Processed . PSMS RVLIS AIGORITHM Sensor Locations: SEE UNIQUE SYSTEM DESCRIPTION FIELD Alarm / Trip Set Points: N/A NI Detector Power Supply Cut-off Power Level N/A i
NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Modes IDW Temperature Compensation For DP Transmitters: Y Level iteference Leg - WET Unique System Desc.: CONNECTIONS TO THE RX VES HEAD AND INCORE INSTRUMENTATION TUBES SENSE RX VES CORE AND INTERNAL DP. REFERENCE LINE TUBING RUNS FROM i
THE INSTRUMENT TUBES TO HICH VOLUME SENSORS WHICH ISOLATE THE RCS '
FROM THE REMAINDER OF THE RVLIS TUBING. CAPILLARY TUBING RUNS FROM THE HIGH VOLUME SENSORS THROUGH THE CNTNT WALL TO HYDRAULIC ISOIATORS RTD'S ARE INSTALLED ON CAPILLIARY LINES FOR CNMNT TEMP.
COMPENSATION. PSMS RECEIVES TRANSMITTER OLTTPUT READING IS INVALID UNLESS RCPS ARE RUNNING 2RCS*LT1322 SENSES DP ACROSS RX VES CORE AND INTERNALS WHEN ANY RCPS ARE RUNNING. NORMAL DP IS 110-112%
!