Letter Sequence Other |
|---|
|
|
MONTHYEARML17278B2371987-02-11011 February 1987
Forwards Human Engineering Discrepancies (Heds) 2CIC-5132 Through 2CIC-5230 from App a to Util 870108 Dcrdr Supplemental Summary Rept.Heds Improperly Reproduced in Original Submittal.Copies Forwarded Directly to R Eckenrode
Project stage: Request
ML20210T5121987-02-11011 February 1987
Forwards Request for Addl Info Re Facility Safety Monitoring Sys Verification & Validation (V&V).Expected Date of V&V Completion Also Requested
Project stage: RAI
ML20215K1301987-04-30030 April 1987
Provides Addl Info Re Verification & Validation of Plant Safety Monitoring Sys Software Components Associated W/ safety-related Reg Guide 1.97 Variables
Project stage: Other
ML20214U0961987-06-0404 June 1987
Forwards Request for Addl Info Re Verification & Validation of Facility Safety Monitoring Sys (Psms V & V)
Project stage: RAI
ML20196A2341988-06-20020 June 1988
Concludes That Based on Licensee Annual Rept of Facility, Changes,Tests & Experiments & 880608 Site Visit, Changes,Tests & Experiments Meet Criteria in 10CFR50.59. Lists Improvements Recommended to Licensee During Visit
Project stage: Other
ML20246M1651989-05-10010 May 1989
Forwards Safety Evaluation Re Plant Safety Monitoring Sys Verification & Validation Plan Submitted by . Hardware Design of Subj Sys Acceptable.Verification & Validation Plan Incomplete & Unacceptable.Info Requested
Project stage: Approval
ML20246G9781989-07-0707 July 1989
Forwards Functional Requirements Matrix,Similarity Document & Description of Continuing Plant Safety Monitoring Sys Verification & Validation Program Accompanied by Graphical Representation of Program,Per 890510 Request
Project stage: Other
ML20248D7451989-09-29029 September 1989
Forwards Supplemental Safety Evaluation Supporting Util 890707 Response to Open Items Re Plant Safety Monitoring Sys Verification & Validation
Project stage: Approval
ML20065P8291990-12-0404 December 1990
Forwards Info Re Status of Plant Safety Monitoring Sys & Spds,Per Generic Ltr 89-06
Project stage: Other
1988-06-20
[Table View] |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P3791999-10-21021 October 1999
Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls
IR 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
ML20217N2521999-10-20020 October 1999
Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC
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
ML20217K7541999-10-15015 October 1999
Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units
ML20217G6751999-10-13013 October 1999
Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1
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
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
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
ML20217G1071999-10-0707 October 1999
Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months
ML20217B0141999-10-0101 October 1999
Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation
ML20216J9161999-10-0101 October 1999
Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves
ML20216J9041999-10-0101 October 1999
Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
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
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
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
ML20212E8751999-09-20020 September 1999
Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl
ML20212E7481999-09-20020 September 1999
Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl
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
ML20212C2191999-09-16016 September 1999
Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03
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-99-098, 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-99-136, 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
ML20211Q4801999-09-0101 September 1999
Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl
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
ML20211J5291999-08-30030 August 1999
Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR
ML20211J5251999-08-30030 August 1999
Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML20211J7381999-08-27027 August 1999
Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid
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
ML20211E9251999-08-23023 August 1999
Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant
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
ML20210V0881999-08-16016 August 1999
Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices
ML20210Q4611999-08-0505 August 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl
ML20210L2181999-08-0202 August 1999
Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl
ML20210N1191999-08-0202 August 1999
Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P3791999-10-21021 October 1999
Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls
ML20217N2521999-10-20020 October 1999
Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC
ML20217K7541999-10-15015 October 1999
Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units
ML20217G6751999-10-13013 October 1999
Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1
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
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
ML20216J9161999-10-0101 October 1999
Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves
ML20216J9041999-10-0101 October 1999
Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
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
ML20212E8751999-09-20020 September 1999
Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl
ML20212E7481999-09-20020 September 1999
Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl
ML20212C2191999-09-16016 September 1999
Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per 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
ML20211J5251999-08-30030 August 1999
Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML20211J5291999-08-30030 August 1999
Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR
ML20211J7381999-08-27027 August 1999
Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid
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
ML20211E9251999-08-23023 August 1999
Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant
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
ML20210L2181999-08-0202 August 1999
Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl
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
ML20210C8011999-07-21021 July 1999
Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001
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
ML20209H3881999-07-14014 July 1999
Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2
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-99-112, 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-99-105, 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
ML20209C4041999-07-0101 July 1999
Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl
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
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
ELV-02056, Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam1990-09-0606 September 1990
Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam
ELV-01599, Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator1990-09-0404 September 1990
Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator
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
ELV-01956, Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request1990-08-30030 August 1990
Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request
ELV-02050, Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required1990-08-30030 August 1990
Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required
ELV-02059, Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B1990-08-30030 August 1990
Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B
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
ML20028G8731990-08-29029 August 1990
Forwards fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.71
ML20059F1501990-08-29029 August 1990
Advises That Permanent Replacement Chosen for Plant Independent Safety Evaluation Group.Position Will Be Staffed Effective 900829
ML20028G8881990-08-24024 August 1990
Withdraws Operator License SOP-10731 (55-60749) Issued to K Gilbert,Who Resigned
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
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
ELV-02022, Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld1990-08-22022 August 1990
Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld
ELV-02028, Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d)1990-08-22022 August 1990
Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d)
ELV-02027, Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively1990-08-20020 August 1990
Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively
ELV-01973, Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical1990-08-14014 August 1990
Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical
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))
ELV-01918, Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion1990-08-0303 August 1990
Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion
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
ELV-01943, Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned1990-07-27027 July 1990
Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned
ELV-01949, Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable1990-07-26026 July 1990
Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable
ELV-01500, Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities1990-07-25025 July 1990
Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities
ML20055H2581990-07-25025 July 1990
Forwards Decommissioning Rept, Per 10CFR50.33(K) & 50.75(b)
ML20055H6441990-07-23023 July 1990
Submits Summary of Snubber Types & Sample Plans for Functional Testing to Be Performed During Sept 1990 Outage
ML20044B0311990-07-13013 July 1990
Forwards Vogtle Electric Generating Plant Unit 1 Reactor Containment Bldg 1990 Integrated Leakage Rate Test Final Rept.
ML20044B1541990-07-12012 July 1990
Responds to NRC 900612 Ltr Re Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Eop Step Deviation Documents to Be Upgraded,Adding More Justification & Temporary Change Issued to Correct EOP Deficiencies
ELV-01867, Responds to Violations Noted in Insp Repts 50-424/90-10 & 50-425/90-10.Corrective Action:Level Indication Error Corrected After Discrepancy Discovered1990-07-12012 July 1990
Responds to Violations Noted in Insp Repts 50-424/90-10 & 50-425/90-10.Corrective Action:Level Indication Error Corrected After Discrepancy Discovered
ML20055F1651990-07-0909 July 1990
Forwards Comments Re NUREG-1410
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
ML20044A8851990-07-0606 July 1990
Forwards Response to NRC Question on Steam Generator Level Instrumentation Setpoints,Per Revised Instrument Line Tap Locations.Tap Location Will Be Changed from Above Transition Cone to Below Transition Cone
ELV-01858, Advises That Full Compliance W/Violation Will Not Be Achieved Until Nov 1990,when Evaluation of VP-2693 Complete1990-07-0606 July 1990
Advises That Full Compliance W/Violation Will Not Be Achieved Until Nov 1990,when Evaluation of VP-2693 Complete
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
ELV-01834, Forwards Response & Comments to Regulatory Effectiveness Review Rept.Encl Withheld (Ref 10CFR73.21)1990-06-28028 June 1990
Forwards Response & Comments to Regulatory Effectiveness Review Rept.Encl Withheld (Ref 10CFR73.21)
ML20044A2791990-06-25025 June 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Indicating Status of Each Generic Safety Issue Encl
ML20043J0171990-06-22022 June 1990
Discusses Corrective Actions for Plant Site Area Emergency, Per 900514 Ltr.Jacket Water High Temp Switches Calibr for Diesel Generators,Using Revised Calibr Procedure
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
ML20043H3061990-06-15015 June 1990
Forwards Rev 3 to ISI-P-014, Inservice Insp Program, for Review & Approval,Per Tech Spec 4.0.5 Re Surveillance Requirements.Rev Includes Withdrawal of Relief Requests RR-45,47,48 & 54
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
ML20043G2071990-06-12012 June 1990
Forwards Amend 18 to Physical Security & Contingency Plan. Amend Withheld (Ref 10CFR73.21)
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
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
1990-09-07
[Table view] |
Text
{{#Wiki_filter:_. --
e g Beaver Valley Power Station Shippingport PA 15077-0004
^
i JOHN D SIEBER (412) 6G5502 Vice Prengtent - Nuclear Operations i
July 7, 1989 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Plant Safety Monitoring System (TAC 64577)
Gentlemen:
Your letter dated May 10, 1989 documented the results of the NRC Staff's audit of the Beaver Valley Power Station Unit 2 (BVPS-2) Plant Safety Monitoring System (PSMS) and requested that information be submitted to resolve PSMS Verification and Validation (V&V) Program open items.
Enclosed are copies of the Functional Requirements Matrix (Attachment A) and the Similarity Document (Attachment B). Also included as Attachment C is a description of our continuing V&V Program accompanied by a graphical representation of the program.
As discussed during the audit, the similarity table was prepared using Plant Vogtle since Plant Vogtle equipment more closely matches the DLC PSMS. Tests that are referenced as being i
performed on South Texas to satisfy the functional requirements q
were also applicable to Plant Vogtle. j 1
Validation testing was performed on the PSMS during our recent l refueling outage. The test procedure used was developed by an !
independent group following the functional requirements matrix and I
development decomposition. Various PSMS discrepancies were i corrected during the first refueling outage under Design Change 1 Package DCP 891. Validation testing was then performed using a test proceduce developed by an independent group, in accordance i with the functional requirements and decomposition.
Performance of the validation testing resulted in the following inconsistencies:
41 Procedural deficiencies 5 Decomposition deficiencies 6 Firmware deficiencies 1 Hardware deficiencies h6 (
4 Miscellaneous I t
2 890707 '
P $$ Eh0hlM 050004 PN 2
Benvor Valley Powar Station, Unit No. 2 Docket NO. 50-412, License No. NPF-73 Plant Safety Monitoring System (TAC 64577)
Page 2 The inconsistencies that occurred during system development that were not discovered during the original software verification activities were identified during the validation - process. An example of an inconsistency involved the thermocouple junction box RTD quality coding algorithm and the manner in which,RTD's with bad quality are addressed. The unresolved inconsistencies have been an61yzed and do not present any operational deficiencies to the system The inconsistencies are documented and will be corrected by future firmware changes as necessary.
The four discrepancies identified during validation. testing that were not completed will be corrected prior to restart following the second refueling outage. These deficiencies do not affect operation of the PSMS. q If you have any comments or questions, please contact me or members of my staff.
Very truly yours, l
J. D. Sieber A-Vice President Nuclear Group cc: Mr. J. Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr. P. Tam, Sr. Project Manager Director, Safety Evaluation &-Control (VEPCO) 1
)
i i
- ATTACHMENT A FUNCTIONAL RE0UIREMENTS MATRIX l
l Apolicable Requirement Aeolicable Document RVLIS Functional Requirements RVLIS.FR.001 Refer to PAMS.FR.001.
RVLIS.FR.002.A Refer to plant CRDR.
. k T kTA display and P. VAR.13.
RVLIS.FR.003.B Refer to PAGE 2 DETAIL DATA display 4 PAGE 3 DETAIL DATA display and P. VAR.14.
RVLIS.FR.003.C Refer to PAGE 2 DETAIL DATA display PAGE 3 DETAIL DATA display and P. VAR.16.
RVLIS.FR.003.D Refer to PAGE 2 DETAIL DATA display PAGE 3 DETAIL DATA display and P. VAR.15.
RV?IS.FR.003.E Refer to 'PAGE 2 DETAIL DATA display PAGE 3 DETAIL DATA displayand P. VAR.02.
RVLIS.FR.003.F Refer to PAGE 2 DETAIL DATA display PAGE 3 DETAIL DATA display and P. VAR.02.
RVLIS.FR.003.G Refer to PAGE 2 DETAIL DATA display PAGE 3 DETAIL DATA display and P. VAR.16.
RVLIS.FR.003.H Refer to PAGE 2 DETAIL DATA display PAGE 3 DETAIL DATA display and P. VAR.15.
RVLIS.FR.003.I Refer to PAGE 2 DETAIL DATA display PAGE 3 DETAIL DATA display and P. VAR.02.
RVLIS.FR.003.J Refer to PAGE 2 DETAIL DATA display PAGE 3 DETAIL DATA display and P. VAR.01.
RVLIS.FR.003.K Refer to PAGE I DETAIL DATA display and P. VAR.13.
RVLIS.FR.003.L Refer to PAGE 2 DETAIL DATA display PAGE 3 DETAIL DATA display and P. VAR.14.
RVLIS.FR.003.M Refer to RV LVL display and P. VAR.17.
RVLIS.FR.003.N Refer to RV LVL display and P. VAR.17.
RVLIS.fR.003.0 Refer to RVLIS.FR.017 RVLIS.FR.004 Refer to RVLIS.FR.003 RVLIS.FR 005 Refer to P. VAR.17 RVLIS.FR.'006 Refer to PAMS.FR.003.A RVLIS.FR.007 Refer to RVLIS.FR.004 RVLIS.FR.008.A Refer to P. VAR.17.
RVLIS.FR.008.B Refer to P. VAR.17.
RVLIS.FR.008.C Refer to P. VAR.17.
RVLIS.FR.008.D Refer to P. VAR.17.
RVLIS.FR.008.E Refer to P. VAR.17.
RVLIS.FR.009.A Refer to P. VAR.17.
RVLIS.FR.009.B Refer to P. VAR.17. i RVLIS.FR.009.C Refer to P. VAR.17. i RVLIS.FR.009.D Refer to P. VAR.17. l RVLIS.FR.009.E Refer to P. VAR.17. ;
l l
- Y
ATTACHMEWT A RVLIS.FR.010 Refer to P.PAMS.FR.001.A.
RVLIS.FR'.011.A Refer to P. VAR.017 RVLIS.FR.011.B Refer to P. VAR.017 RVLIS.FR.011.C Refer to P. VAR.017 RVLIS.FR.011.D Refer to P. VAR.02 RVLIS.FR.011.E Refer to P. VAR.01' RVLIS.FR.011.F Refer to P. VAR.016 RVLIS.FR.012 Refer to P.PAMS.FR.006 RVLIS.FR.013 Refer to P.PAMS.FR.007.A and B.
RVLIS.FR.014 Refer to'P.PAMS.FR.008.A.
RVLIS.FR.015 Refer to P. VAR.17.
RVLIS.FR.016 Refer to P.PAMS.FR.009.
RVLIS.FR.017.A Refer to P.PAMS.FR.010.
RVLIS.FR.017.B Refer to P.PAMS.FR.010.E 1
s s
4 h
l I
l I
l l
l
n
- ATTACHMENT A FUNCTIONAL RE0VIREMENTS MATRIX Abolicable Requirement Applicable Document PAMS Fungtional Requirements P.PAMS.FR.001.A Refer to EQDP ESE-53 and 53B for the RPU/DPU qualification test results. Refer to ESE-61B l for the plasma display qualification results.
Refer to the plant equipment qualification files for the qualification status of the'other portions of the Category I and 2 channels routed via the PSMS.
P.PAMS.FR.001.8 Refer to P.PAMS.FR.001.A.
P.PAMS.FR.001.C Refer to P.PAMS.FR.001.A.
P.PAMS.FR.001.D Refer to P.PAMS.FR.001.A.
P.PAMS.FR.002.A Refer to PSMS Technical Manual, Volume 1, Figure 1-1.
(Document 2501.405-001-003.)
P.FAMS.FR.002.B Refer to the plant CRDR.
P.PAMS.FR.002.C Refer to PSMS Technical Manual, Volume 1, Figure 1-1.
(Document 2501.405-001-003)
P.PAMS.FR.002.D Refer to drawing 2032338 Rev 4 sheet 6 P.PAMS.FR.002.E Refer to P. VAR.001 : RCS Pressure (WR)
P. VAR.002 : WR Hot Leg Temperature P. VAR.003 : WR Cold Leg Temperature P. VAR.004 : Steamline Pressure P. VAR.005 : PP DWST Level P. VAR.006A: Neutron Flux-Lower Range P. VAR.006B: Neutron Flux-Upper Range P. VAR.007 : Containment Hyrogen
" VAR.008 : Containment Pressure (XR)
P.'fAR.009 : Primary Safety Valve Status
- P. VAR.010 : SG Safety Valve Status d
P. VAR.011 : CCW Header Pressure
- P.' VAR.012 : 'CCW Header Temperature
' P. VAR.013 : RCP Motor Status l P. VAR.014 : Hydraulic Isolators l P. VAR.015 : DP Transmitters l P. VAR.016 : Capillary Line RTDs i P. VAR.017 : RVLIS 1 P. VAR.018 : Reference Junction j Box RTDs i P. VAR.019 : Core Exit Thermocouple !
, P. VAR.020 : RCS Subcooling l P. VAR.021 : Reactor Trip i
Breaker Status ;
P.PAMS.FR 002.F Refer to P.PAMS.FR.002.E. ;
Refer to drawing 2031991 Rev 3 sheet 21,30 and31.
~
P.PAMS.FR.003.A P.PAMS.FR.003.B Refer to the PSMS Technical Manual, Volume 1, Section 2.3.(Document 2501.405-001-003)
P.PAMS.FR.003.0 Refer to P.PAMS.FR.003.A I
_j
ATTACHMENT A 4
P.PAMS.FR.004.A Refer to the following maintenance surveillance procedures:
2MSP-3.03-I :PSMS Input Checks of RPU A Channel III .
*RJB RTDs : TE-A1,A2,A3
- Core Exit T/Cs': TE-01,02,04,05,10,11, 13,14,15,16,20,21, 22,23,24,25,26,28, 33,34,39,40,41,47, 48,49
- Capillary Line RTDs : TE-1313,1314,1315, 1316,1317,1318, 1319
*DP Transmitters : LT-1310,1311,1312
*RCS Pressure (WR) : PT-440
*PP DWST Level : LT-104A3
*Steamline Pressare : PT-475,485,495 2MSP-3.05-I :PSMS Input checks of RPU A Channel I
- WR Hot Leg ~ Temperature : TE-413,423,433
*RCS Pressure (WR) : PT-442
- Containment. Pressure (XR) : PT-106A .
- Neutron Flux-Lower Rng : NFLUXL (Tr A)
- Neutron Flux-Upper Rng : ' NFL!JXU (Tr A)
- Containment Hydrogen : HA-100A 2MSP-3.06-I :PSMS Input Checks of RPU B Channel II
*WR Cold Leg Temperature :.TE-410,420,430
- Containment Pressure (XR) : PT-106B
- Containment Hydrogen : HA-100B'
-*Neutron Flux-Lower Rng : NFLUXL (Tr 8)
- Neutron Flux-Upper Rng. : NFLUXU (Tr B) 2MSP-3.04-1 :PSMS Input Checks of' RPU B Channel IV
*RJB RTDs : TE-B1,B2,83
- Core Exit T/Cs : TE-03,06,07,08,09,12,17, 18,19,27,29,30,31,32,
. 35,36,37,38,42,43,44, 45,46,50,51
- Capillary Line RTDs : TE-1323,1324,1325,
. 1326,1327,1328, 1329
*DP Transmitters : LT-1320,1321,1322
*RCS Pressure (WR) : PT-441
*Steamline Pressure : PT-476,486,496
*WR Hot Leg Temperature : TE-423A 2MSP-3.07-I :PSMS Input Checks of RPU N1 .
- Hydraulic Isolators : LIS-1310,1311,1312, 1320,1321,1322
*RCP Motor Status : P-21A,21B,2]C 4
(
I i
. ATTACHMENT A )
P.PAMS.FR.004.B 2MSP-3.03-1 :PSMS Input Checks of RPU B Channel III
*CCW Header Pressure : PT-150A,150B,150C j
- Primary Safety Valve Status:
RV-551A,551B,551C
*SG Safety Valve Status : SV-105A,105B,105C 2MSP-3.05 I. :PSMS Input Checks of RPU A Channel I .
*CCW Header Temperature : TE-130A,130B,130C
*SG Safety Valve Status : SV-101A,1018,101C ]
SV-103A,1038,103C
- Reactor Trip Breaker Status :52-RTB 2MSP 3.06-1 :PSMS Input Checks of RPU B Channel II
- SG Safety Valve Status : SV-102A,102B,102C SV-104A,104B,104C 2MSP-1.04-I :PSMS Input Checks of RPU B Channel IV 4
- Reactor Trip Breaker Status : 52-RTA P.PAMS.FR.004.C Refer to P.PAMS.FR.001.A. i P.PAMS.FR.004.D Refer to P.PAMS.FR.001.A.
P.PAMS.FR.005.A Refer to P.PAMS.FR.002.E. h P.PAMS.FR 005.B Refer to P.PAMS.FR.002.E.
P.PAMS.FR.006.A Refer to South Texas Project QDPS procedure DSPD.0986.0 tests 5.0 and 11.0.
P.PAMS.FR.006.B Refer'to South Texas Project QDPS procedure DSPD.0986.0 tests 4.0 and 11.0.
P.PAMS.FR.007.A Refer to South Texas Project QDPS procedure DSPD.0986.0 test 9.0 and 11.0.
P.PAMS.FR.007.B Refer to South Texas Project QDPS procedure DSPD.0986.0 test 9.0 and 11.0.
P.PAMS.FR.008.A Refer to South Texas Project QDPS procedure SPEC.1186.0 test 6.1. j P.PAMS.FR.009.A Refer to P.PAMS.FR.004. l P.PAMS.FR.009.B Refer to P.PAMS.FR.002.A l P.PAMS.FR.010.A Refer to Beaver Valley Unit 2 USAR, Figure 8.3.14 I
, for the source of power to the PSMS. l
*RPU A ,DPU A - Protection Set 1 I
*RPU B, DPU B - Protection Set II !
, *RPU C - Protection Set III
*RPU D - Protection Set IV I P.PAMS.FR.010.B Refer to P.PAMS.FR.010.A.
P.PAMS.FR.010.C Refer to South Texas Project QDPS procedure >
SPEC.1186.0 test 6.4. ;
P.PAMS.FR.011.A Refer to P.PAMS.FR.001 !
P.PAMS.FR.004 I P.PAMS.FR.005 ;
P.PAMS.FR.010 '
P.PAMS.FR.012.A Refer to P.PAMS.FR.001 P.PAMS.FR.004 i P.PAMS.FR.005
ATTACHMENT B .
.(pmoarison of Beaver Vallev Unit 2 & Plant' Voatle PSMS Beaver Vallev Unit 2 ht Vootle . i System *Idantical equipment ,
-Overview qualification data packages j
*WCAP-11340 applicable 1
)
*Similar hardware configuration i
- Equivalent system level software
]
*Similar application a' <ithms *Similar application algorithms (Generic design (Ger.eric design specifications utilized- specifications utilized- !
3 vs 4 loop configuration) 3 vs 4 loop configuration)' j
- Approx 120 analog inputs
- Approx 250. analog inputs
- Approx 20 digital inputs
- Approx 300 digital inputs .)
- Plant specific keyboard layout
- Plant specific keyboard layout (Different display hierarchy) (Different display hierarchy)
(
- Generic PSMS Design Specification l
t
*Similar Factory Acceptance Test
]
l l
1 i
)
i l
1 l
'~
ATTACHMENT B .!
1 1
1 4
Beaver Valley Unit 2 Plant Voatle Remote *1 CP/ vital bus I *2 cps / vital bus I I Processina 1 CP/ vital bus II 2 cps / vital bus II 1 Malt 1'CP/ vital bus III 1 CP/ vital bus III !
( RPU ) 1 CP/ vital bus IV 1 CP/ vital bus IV
*2 Class IE Dual Bay cabinets *2 Class IE Dual Bay cabinets i 1 non-Class IE cabinet 2 Class IE Single Bay cabinet l 1 non-Class IE cabinet j i
- Identical 100 RTD input cards
- Identical 200 RTD input cards
- Identical 4-20 ma input cards i
- Identical contact' input cards 1 I
*!dentical 0-10 V input cards !
- Intel SBC-8605 CP .
- Intel SBC-519 digital I/O j
,(
- Modified Data I
- Translation DT-1742 A/D l
- Intel SBC-544 Communication Control I
- Intel SBC-428 PROM board
- Micro Memory HM 8086/64 CMOS RAM board
- Identical Self Health board (Westinghouse design)
- Equivalent system level software
*Similar application algorithms Similar application algorithms (Generic d + p (Generic design l specifications utilized) specifications utilized)
*Similar factory Acceptance Tests 1
L1 ATTACHMENT B :
(
Beaver Vallev Unit 2 Plant Voatle Dftabase *1 CP/ train *1 CP/ train Processina Unit *1 Class IE Dual Bay cabinet 32 Class 1E Dual Bay cabinets.
( DPU )
*RS-422/232 Conversion board input (RPU to DPU)
- Encode / Decode RS-422 Datalink board (DPU to Display)
- Intel SBC-8605 CP
- Intel SBC-428 NVRAM storage
- Identical Self Health board
- Intel SBC-519 Digital I/O j i
- Data Translation DT-104. D/A
- Intel SBC-88/45 Communication Control ;
l'
.(<
- Intel SBC-428 PROM board
- Micro Memory MM 8500CC/256K CMOS RAM board
*Similar application algorithms *Similar application algorithms (Generic design (Generic design .l specifications utilized) specifications utilized)
- Equivalent system level software
*Similar Factory Acceptance Tests i
h__ . _ _ _ _ _ . - _ _ _ - _ _ . _ _ _ _ _ . _ _ . . . _
ATTACHMENT B'
( Beaver Vallev Unit 2 Plant Voatle Disolav *1 module / train U.Dit
- Intel.SBC-8605 CP
- Identical Display Interface (Westinghouse design)
- Micro Memory MM 8500CC/256K CMOS RAM board.
- Intel SBC-88/45 Communication Control
- Identical Utility Interface Control
- Electro Plasma Dot Matrix Display ( 512x512 )
- Plant specific display pages
- Plant specific display. pages (Different display hierarchy) (Different display hierarchy)
*Similar Facte.y Acceptance Tests, t
i Keyboard
- Identical Keyboard Interface ;
board
- Plant specific keyboard layout
- Plant specific keyboard layout (Different display hierarchy) (Different display hierarchy)
*Similar Factory' Acceptance Tests i
l 1
i
.(
l l
l 4
ATTACHMENT C PSMS (TAC 64577 RESPONSE)
I. INTRODUCTION The plan described below will be implemented for future software changes on the PSMS. A graphical representation of the PSMS software V&V plan' is provided in Figure 1. The software verification and validation portions of the plan will be performed by a group (s) that is independent from the design team. The PSMS software change V&V plan is scheduled to be implemented prior to start-up following the second refueling outage, II. SOF'NARE VERIFICATION The system verification process verifies the functionality of the software entities. Verification techniques used in software development can fall into two basic categories, review and testing.
A. Software Review Three types of reviews that can be used in the verification of software are Design Specification reviews, Source Code reviews and Functional Test reviews. '
- 1. Design Specification Review l l
The comparison of a Software Design Specification for a subsystem, module, or unit to the Design Specification of the 1 component above it is performed to ensure that all of the !
performance requirements stated in the higher level document are met.
l
- 2. Source Code Review {
During the Source Code review, the software is examined by qualified independent personnel and operation of the software is deduced and compared with the expected operation. In effect, the operation of the software is evaluated to confirm .
that it agrees with the specification. )
Source code reviews verify the transformation from a Design Specification into high level code.
- 3. Functional Test Review A functional test review is a review by the verifier of the ,
functional test results which were generated by the designer.
l The review of the test results provides a high degree of
! assurance that the software performs the functions specified in the design requirements. ,
'i ATTACHMENT C 'I
, PSMS (TAC 64577 RESPONSE) 1 B. Software Testing i Software testing can be divided into two categories, structural ;
and functional. j a
- 1. Structural Testing Structural testing comprehensively exercises the' software program code and its component logic structures. The' ;
functionality of the program is' verified in conjunction with the internal structure utilized within the program to implement the required function. 9 Structural testing requires that the verifier inspect.the code and understand how it functions before selecting the test inputs. The test. inputs are chosen to exercise all the possible branches within the software entity. If this is not possible, the test inputs fare then chosen to exercise i i
every statement within the software entity. For example, if a trigonometric function is ' calculated in several'different ways, depending on the range of the input argument,-then the ;
test inputs include tests for the argument-in each of these ?
ranges, as well as on the boundaries between ranges. For example, they exercise the upper limit, the lower limit, and at least one intermediate value within each range.
- 2. Functional Testing
)
l In the functional approach to program testing, the internal structure of the program is. ignored during the test l selection. Tests are constructed from the functional !
properties of the program which are defined in the Design Specification. Functional testing is the method most frequently used at the module or subsystem level. . Examples of functional testing include random testing and special cases by function.
>l Random testing is the method of applying a test input sequence chosen at random. The method can be used in the following circumstances: to simulate real time events; to increase the confidence level in the correctness of a very complex module; to test a subsystem or a system where it-is not necessary to test all the possible paths; to get some quantitative measure on the accuracy of a numeric l calculation; or to. get a measure of the average time l required by some calculation.
l 1
l ATTACHMENT C PSMS (TAC 64577 RESPONSE)
Following the above methodologies, the software will be verified and j then entered into the library. The following activities will be ,
performed to provide the software baseline: i
- Take credit for duplicate software on other installations where the Vendor's software verification program was conducted. j 1
- Perform a verification program using a source code review technique !
discussed above on the " differences" software using a group independent from the design group.
III. SYSTEM VALIDATION A. Validation Philosophy The system validation process is performed to demonstrate the system functionality. The system validation test results demonstrate that the system design meets the system functional requirements. Hence, any inconsistencies that occurred during the system development in this area that were not discovered during the software verification ,
activities can be identified through the validation process. 1 B. Validation Testing Overview
{
Validation testing compliments the verification process by ensuring that the system meets its functional requirements.
The major phases of the validation process can include the following:
- 1. Functional requirements testing - ensures that the final system meets the functional requirements. A comprehensive functional requirements decomposition is conducted on all system functional requirements from which the validation test requirements originated. ;
1
- 2. Abnormal mode testing -
ensures that the design operates properly under abnormal operating conditions. As an example, the testing may include off-scale high or off-scale low simulation to ensure that proper PSMS response is obtained.
3 System Prudency Review / Testing - ensures that ga4 design practice was utilized in the design and implementa. ion of critical design areas of the system. The Review / Testing requires that the internals of the system design and implementation be analyzed in detail.
l 4. Specific Man-Machine Interface testing -
ensures that the j man-machine interface utilized to modify the system data base at the maintenance terminal performs properly.
i ATTACHMENT C i 1
, PSMS (TAC 64577 RESPONSE)
The macroscopic top-down. functional requirements phase of validation j process treats the system as a black box whereas the prudency review I '
phase requires that the internal structure of the integrated software / hardware system be analyzed in more detail. Due to the dual approach, validation testing provides a level of thoroughness J and testing accuracy which enhances the possibility of detection of j deficiencies that could have occurred during the design process but not discovered during verification. Validation may be performed on verified software residing within the PSMS target hardware or on a test jig.
Following the specification of tests associated with the 4 major phases, detailed validation' test procedures are written which i specify the detailed engineering tests and required system ;
responses. The tests are then conducted on the system target hardware or a test jig which incorporates the' system verified software. Deviation between the system response and the desired ,
results are identified and officially recorded as a Validation j Trouble Report. Typically, the trouble report is then returned to the design group for resolution by. one or more of the following techniques: software change; ' hardware change; validation test j modification; functional requirements / decomposition modification; or no problem identified. If a software or hardware change is required, the revised software must be reverified and subjected.to a validation retest. l l
C. Validation Testing of Software Modifications j Validation testing may be performed on a test jig or the PSMS target j hardware. A test jig may be used because the PSMS is made up of I multiple independent micr, processor based subsystems. 'The independence of these subsystems allows a' test jig to be made up of a partitioned subset of the entire set of subsystems, as long as the data flowing into the subset exactly simulates the data flow in the actual PSMS with respect to timing, content, and organization. ,
i The rationale for performing the validation testing on a test jig for software modifications is that some software modifications may affect as few as one of the PSMS subsystems. As long as the interactions with the other portions of the system are well understood, and are determined to have no impact on previously performed testing, validation testing on a subset of the PSMS will be as effective in assuring correct system performance as testing on the integrated system.
In order to maintain the independence of the validation test and to assure the traceability of the validation test to the actual system, the following is required of a test jig:
- 1. The configuration of the test jig is defined by the validation ,
group. The conflict of the testing being constrained by a '
hardware configuration specified by system designers is avoided.
ATTACIBGENT-C PSMS (TAC 64577 RESPONSE)
- 2. The hardware environment in which the software under test must operate shall have a traceable' configuration to the PSMS target hardware. This means that the. microcomputer board set, the PROMS, the environment, etc., shall be the same as the PSMS.
target hardware. ' Input signals to the subsystem shall be defined so as to appear to the software to be actual PSMS signals. Any use of hardware boards (CPU, memory) different from the actual PSMS shall be analyzed to demonstrate that their use does not invalidate any testing..
3 A documented configuration of the test jig shall be maintained and referenced in the validation test plan to provide an audit trail.
l IV. VERIFICATION AND VALIDATION TEAM ORGANIZATION The verification and validation team is independent of the design team developing the PSMS asftware. The use of two independent teams introduces diversity to the process of software development and reduces the probability of undetected errors. Additionally such a scheme requires the designer. to produce sufficient and unambiguous documentation before validation. can take place (e.g. functional requirements, design specifications, etc.).
l A. Verification Team The typical functions of the verification team are as follows:
- 1. Review the software design specifications received from the l design team.
- 2. Evaluate the software changes to determine content and scope.
I 3 Using the software design specification develop software test specifications, perform software testing and issue trouble reports if necessary.
- 4. Following the resolution of trouble reports, repeat software testing as required.
- 5. Perform software librarian functions for the storage .and configuration control of the verified software.
B. Validation Team The typical functions of the validation team are as follows:
- 1. Generate a detailed functional requirements decomposition document which specifies the type of tests that must be conducted in order to demonstrate the system functional requirements are met.
ATTACHMENT C :
, PSMS (TAC 64577 RESPCNSE) ;
.l
- 2. Using the decomposition document as the basis, generate detailed validation testL procedures (e.g. identify . specific terminal screw inputs, required voltage, current and resistance-inputs, etc.). .
3 Conduct the validation tests on the PSMS target system or a test ;
jig. J
- 4. Compare validation test results with desired test results and issue Validation Trouble Report for any deviations identified.
- 5. Following the resolution of. trouble reports, repeat validation testing as required.
V. V&V PLAN Figure 1 depicts the .V&V plan for future software changes. The following summary presents the activities of the V&V plan, described-herein.
A request for change is processed.
1 The center blocks of activities represent-the Design Team's efforts for J implementing the changes.
The functional requirements and design specifications are changed as necessary and forwarded to the validation team. 1 l
The firmware modifications are performed and then the design !
documentation along with the source code is forwarded to the 4 verification team.
The verification team activities, sho,m on the right of Figure 1, are I performed by a group independent from the design team. l i
A change impact analysis is performed to determine the impact of the
' software changes on the other software components.
A software verification is performed on the source code affected by the change.
Any trouble reports are processed back to the design team to correct any software deficiencies. l i l The verified software is then stored in the V&V library.
The validation team activities, shown on the left side of Figure 1, are i performed by a group independent from the design team. J A change impact analysis is performed to evaluate the impact the change j has on the system.
j i
l j
1 1
. ....:.. ATTACIBE3fT C l
, PSMS (TAC 64577 RESPONSE) ,
The. functional. decomposition. document is' revised to consider the changes and this information is used to r6. vise the validation test procedures as necessary.
When all conditions of the validation, design, and verification teams have been. satisfied, factory acceptance / validation. testing is performed. -{
Trouble reports generated by the validation team, if any, are processed' . ~
back.to the design group for resolution.
When the. factory acceptance / validation testing is completed satisfactorily,'the results are documented and the V&V-activities for' the particular change are complete. !
i 4
I l
1 l
l l
1 i
ATTACHMENT'C
. UERIFICAT TI M FIAN Sof I gf FISIE 1 CHANGE 1 '
e i e 4 l 8 4-Ipcgdesimpactanalysis i S IM $ecesfan,138tei.i>nis
; i i i l l v l l Age S FIlWMARE 4 i i MODIFICATIONS Mfbt ! !
"W5 W" as necessary l l i '
l i '
i
" !i 'd b V fM A 1 '
u necekarv , ,
VES i
i
'/:NO i i l l < .
I e i VERIFID - gred in SOFTl44RE l
i i e i l l i e i i e i o l " l o l MC 0 l A 'A ken f i
l l 1 e 1
i i
/ l l i
VES i
- A e i e I i NO ! s
' i (ay j l
j l
l UALI Mil m IIAM i DESIGN TM N i VIRITICATIM TDM !
i a j
i}}