|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) ML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient ML20212F2111999-09-22022 September 1999 Forwards Review of SG 90-day Rept, South Texas Unit-2 Cycle 7 Voltage-Based Repair Criteria Rept, Submitted by Util on 990119 NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER ML20212D9171999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of South Texas Project & Identified No Areas in Which Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through Mar 2000 & Historical Listing of Plant Issues,Encl ML20216F5471999-09-15015 September 1999 Discusses 990914 Meeting Conducted at Region Iv.Meeting Was Requested by Staff to Introduce New Management Organization to Region IV & to Discuss General Plant Performance & Mgt Challenges IR 05000498/19990121999-09-14014 September 1999 Forwards Insp Repts 50-498/99-12 & 50-499/99-12 on 990816-19.Three Violations Occurred & Being Treated as Ncvs. Areas Examined During Insp Included Portions of Access Authorization & Physical Security Programs 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER ML20211P8201999-09-0909 September 1999 Forwards SE Authorizing 990224 Submittal of First 10-year Interval ISI Program Plan - Relief Request RR-ENG-24,from ASME Section XI Code,Table IWC-2500-1 NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) ML20211P7671999-09-0909 September 1999 Forwards SER Authorizing Licensee 990517 Alternative Proposed in Relief Request RR-ENG-2-8 to Code Case N-491-2 for Second 10-year Insp Interval of South Texas Project, Units 1 & 2,pursuant to 10CFR50.55a(a)(3)(i) ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 IR 05000498/19990141999-09-0303 September 1999 Forwards Insp Repts 50-498/99-14 & 50-499/99-14 on 990627-0807.Apparent Violations Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) ML20212A4351999-08-27027 August 1999 Discusses Investigation Rept OI-4-1999-009 Re Activites at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination Complaint. Allegation Not Substantiated.No Further Action Planned NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 ML20211F4421999-08-24024 August 1999 Forwards SE Authorizing Licensee 990513 Request for Relief RR-ENG-2-13,seeking Relief from ASME B&PV Code Section Xi,Exam Vessel shell-to-flange Welds for Second ISI Intervals ML20211F5031999-08-23023 August 1999 Forwards SE Authorizing Licensee 990315 Request for Relief RR-ENG-30,seeking Relief from ASME B&PV Code,Section Xi,Nde Requirements Applicable to Stp,Unit 2 SG Welds ML20212A4391999-08-17017 August 1999 Discusses Investigation Rept OI-4-1999-023 Re Activities at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination for Initiating Condition Report to Document Unauthorized Work Practices ML20210U1271999-08-16016 August 1999 Forwards Insp Repts 50-498/99-08 & 50-499/99-08 on 990517-21 & 0607-10.No Violations Noted.Corrective Action Program Was Reviewed ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 ML20210F3851999-07-26026 July 1999 Forwards Exam Repts 50-498/99-301 & 50-499/99-301 on 990706- 15.Exam Included Evaluation of 9 Applicants for SO Licenses & 8 Applicants for RO Licenses 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062F8821990-11-15015 November 1990 Ack Receipt of 901017 Response to Violations Noted in Insp Repts 50-498/90-28 & 50-499/90-28 IR 05000498/19900101990-11-0909 November 1990 Ack Receipt of 900711 & 1003 Ltrs Informing NRC of Corrective Measures for Weaknesses Noted in Insp Repts 50-498/90-10 & 50-499/90-10 ML20062F8911990-11-0707 November 1990 Advises of Postponement of Soviet Delegation Visit to Plant Site Due to Unavailability of Seats on Aeroflot. Representatives Will Try Again to Obtain Seats in 2 Wks.Nrc May Reschedule Visit to Plant If Representatives Successful ML20216J9651990-11-0606 November 1990 Concludes That Actions Proposed in Util Response Met Intent of Generic Ltr 88-17, Loss of Dhr ML20062E3841990-11-0606 November 1990 Advises That 900914 Proposed Rev to Exam Schedule for Class 1 Nozzles Complies W/Asme Section XI Code XI-1-86-74 ML20058E2941990-11-0202 November 1990 Forwards Summary of Staff Understanding of Current Status of Generic Safety Issues Which Remain Unimplemented IR 05000498/19900311990-11-0101 November 1990 Discusses Insp Repts 50-498/90-31 & 50-499/90-31 on 900912- 21 & Forwards Notice of Violation IR 05000498/19900051990-10-31031 October 1990 Ack Receipt of 901001 Request for Extension of Corrective Action Implementation Date for Violations Noted in Insp Repts 50-498/90-05 & 50-499/90-05.Commitment to Implement Corrective Actions Prior to Aug 1991,acceptable ML20058A5941990-10-18018 October 1990 Requests Addl Info Re Review of Probability Safety Assessment of Facility ML20059M7001990-09-28028 September 1990 Forwards Insp Repts 50-498/90-27 & 50-499/90-27 on 900813-17.No Violations or Deviations Noted ML20059N7721990-09-24024 September 1990 Forwards Safety Evaluation Accepting Util First 10-yr Interval Inservice Insp Program Plan ML20059K9321990-09-18018 September 1990 Forwards Insp Repts 50-498/90-28 & 50-499/90-28 on 900730- 0808 & Notice of Violation.Violation Re Mixed Bed Demineralizer of Particular Concern Because Potential for Inadvertent Reactivity Not Mitigated ML20059J9971990-09-13013 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 901010 IR 05000498/19890471990-08-31031 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/89-47 & 50-499/89-47.Review Will Be Documented in Insp Repts 50-498/90-30 & 50-499/90-30 ML20059F0921990-08-30030 August 1990 Forwards Request for Addl Info Re Fire Protection Modeling in Probability Safety Assessment.Answers to Questions Will Form Basis for 900919 Meeting in Rockville,Md ML20059D5861990-08-27027 August 1990 Confirms 900830 Mgt Meeting in Region IV Ofc to Discuss Scenario Exercise Weaknesses Identified During Apr 1990 Emergency Exercise at Plant ML20056B3971990-08-20020 August 1990 Forwards Partially Withheld Insp Repts 50-498/90-22 & 50-499/90-22 on 900604-08 & Notice of Violation ML20056B3191990-08-17017 August 1990 Forwards Insp Repts 50-498/90-24 & 50-499/90-24 on 900701-0801.No Violations or Deviations Noted ML20056A7791990-08-0808 August 1990 Discusses Licensee Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Justification for Differences in Program & Generic Ltr Should Be Incorporated Into Program Description ML20056A7751990-08-0707 August 1990 Forwards Request for Addl Info Based on Review of Probability Safety Assessment at Plant ML20056A7981990-08-0303 August 1990 Advises That 900122 Relief Requests Re Pump & Valve Inservice Test Plan Acceptable & That Stroke Time Criteria Need Not Be Documented in Plan Itself,If Included Elsewhere in Procedures.Any Revs to Plan Should Be Provided to NRC ML20056A7961990-08-0303 August 1990 Advises That Util Response to Generic Ltr 88-06 Re Implementation of Spds,Acceptable ML20055G8191990-07-19019 July 1990 Forwards Insp Repts 50-498/90-23 & 50-499/90-23 on 900601-30.No Violations or Deviations Noted IR 05000498/19900011990-07-19019 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/90-01 & 50-499/90-01 ML20055G0771990-07-13013 July 1990 Advises That Most Portions of Rev 16 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Portions Noted in Encl That Decrease Effectiveness of Plan Should Be Resubmitted.Encl Withheld (Ref 10CFR73.21) ML20055F5831990-07-10010 July 1990 Advises That 900601 Rev 10 to Safeguards Contingency Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20055F7431990-07-0505 July 1990 Advises That Util 900216 Response to Bulletin 89-003, Potential Loss of Required Shutdown During Refueling Operations, Acceptable ML20059M8401990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248H5811989-10-0505 October 1989 Forwards Summary of 891003 Meeting in Region IV Ofc Re Activities Authorized by Licenses NPF-76 & NPF-80 ML20248H2151989-10-0505 October 1989 Forwards Insp Repts 50-498/89-31 & 50-499/89-31 on 890814-25.No Violations or Deviations Noted IR 05000498/19890171989-09-29029 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/89-17 & 50-499/89-17 ML20248C6901989-09-28028 September 1989 Forwards Insp Repts 50-498/89-35 & 50-499/89-35 on 890814-18 & Notice of Violation ML20248C6101989-09-27027 September 1989 Forwards Insp Repts 50-498/89-33 & 50-499/89-33 on 890821-25.Violations Noted,But No Citations Will Be Issued, Per NRC Policy ML20248C6731989-09-26026 September 1989 Forwards Insp Repts 50-498/89-30 & 50-499/89-30 on 890801-31.No Violations or Deviations Noted ML20247R3021989-09-22022 September 1989 Forwards Insp Repts 50-498/89-37 & 50-499/89-37 on 890911-15.Violations Noted.No Citation Issued Per Section V.A of NRC Enforcement Policy ML20248G9491989-09-21021 September 1989 Forwards Unexecuted Amend 6 to Indemnity Agreement B-108, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248E6121989-09-21021 September 1989 Forwards Safety Evaluation Re Deletion of Dynamic Rod Drop Test,Static Rod Cluster Control Assembly (Rcca) Test & Rcca Below Bank Position Measurement Tests Based on Review of Util 890728 Submittal.Deletion Acceptable ML20247H5281989-09-12012 September 1989 Forwards Insp Repts 50-498/89-36 & 50-499/89-36 on 890821-25 & Notice of Violation ML20247K2001989-09-12012 September 1989 Advises That Rev 1 to Licensee Licensed Operator Requalification Program Meets 10CFR50.59 Requirements & Acceptable.Revised Rule Stated in Generic Ltr 87-07 Offered as Alternative to Submitting Program for Review ML20247D4521989-09-11011 September 1989 Forwards Insp Repts 50-498/89-25 & 50-499/89-25 on 890724-28 & 0807-11.No Violations or Deviations Noted. Independent Safety Engineering Group Appeared to Be Below Goal for Performing Direct Plant Observations ML20247B6891989-09-0101 September 1989 Forwards Summary of 890825 Meeting W/Util in Region IV Ofc Re Activities Authorized Under Licenses NPF-76 & NPF-80. Better Understanding of Util Operations,Refueling Outage & Mgt Programs Provided ML20246M9411989-08-31031 August 1989 Forwards Insp Repts 50-498/89-22 & 50-499/89-22 on 890710-14.No Violations or Deviations Noted ML20247A5621989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executive Meeting on 890818 at Univ of Texas.Agenda & List of Attendees Encl ML20246E9721989-08-25025 August 1989 Forwards Insp Repts 50-498/89-26 & 50-499/89-26 on 890718-20.No Violations or Deviations Noted ML20246A3271989-08-16016 August 1989 Forwards Insp Repts 50-498/89-28 & 50-499/89-28 on 890731-0804.No Violations or Deviations Noted ML20245L5451989-08-15015 August 1989 Forwards Insp Repts 50-498/89-17 & 50-499/89-17 on 890601-30 & Notice of Violation ML20245H3801989-08-11011 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/89-10 & 50-499/89-10 ML20245J5211989-08-10010 August 1989 Forwards Insp Repts 50-498/89-15 & 50-499/89-15 on 890607-30 & Notice of Violation.Actions Taken Re Previous Insp Findings Examined 1990-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient ML20212F2111999-09-22022 September 1999 Forwards Review of SG 90-day Rept, South Texas Unit-2 Cycle 7 Voltage-Based Repair Criteria Rept, Submitted by Util on 990119 ML20212D9171999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of South Texas Project & Identified No Areas in Which Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through Mar 2000 & Historical Listing of Plant Issues,Encl ML20216F5471999-09-15015 September 1999 Discusses 990914 Meeting Conducted at Region Iv.Meeting Was Requested by Staff to Introduce New Management Organization to Region IV & to Discuss General Plant Performance & Mgt Challenges IR 05000498/19990121999-09-14014 September 1999 Forwards Insp Repts 50-498/99-12 & 50-499/99-12 on 990816-19.Three Violations Occurred & Being Treated as Ncvs. Areas Examined During Insp Included Portions of Access Authorization & Physical Security Programs ML20211P8201999-09-0909 September 1999 Forwards SE Authorizing 990224 Submittal of First 10-year Interval ISI Program Plan - Relief Request RR-ENG-24,from ASME Section XI Code,Table IWC-2500-1 ML20211P7671999-09-0909 September 1999 Forwards SER Authorizing Licensee 990517 Alternative Proposed in Relief Request RR-ENG-2-8 to Code Case N-491-2 for Second 10-year Insp Interval of South Texas Project, Units 1 & 2,pursuant to 10CFR50.55a(a)(3)(i) ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 IR 05000498/19990141999-09-0303 September 1999 Forwards Insp Repts 50-498/99-14 & 50-499/99-14 on 990627-0807.Apparent Violations Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212A4351999-08-27027 August 1999 Discusses Investigation Rept OI-4-1999-009 Re Activites at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination Complaint. Allegation Not Substantiated.No Further Action Planned ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 ML20211F4421999-08-24024 August 1999 Forwards SE Authorizing Licensee 990513 Request for Relief RR-ENG-2-13,seeking Relief from ASME B&PV Code Section Xi,Exam Vessel shell-to-flange Welds for Second ISI Intervals ML20211F5031999-08-23023 August 1999 Forwards SE Authorizing Licensee 990315 Request for Relief RR-ENG-30,seeking Relief from ASME B&PV Code,Section Xi,Nde Requirements Applicable to Stp,Unit 2 SG Welds ML20212A4391999-08-17017 August 1999 Discusses Investigation Rept OI-4-1999-023 Re Activities at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination for Initiating Condition Report to Document Unauthorized Work Practices ML20210U1271999-08-16016 August 1999 Forwards Insp Repts 50-498/99-08 & 50-499/99-08 on 990517-21 & 0607-10.No Violations Noted.Corrective Action Program Was Reviewed ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210F3851999-07-26026 July 1999 Forwards Exam Repts 50-498/99-301 & 50-499/99-301 on 990706- 15.Exam Included Evaluation of 9 Applicants for SO Licenses & 8 Applicants for RO Licenses ML20210D9011999-07-23023 July 1999 Forwards Safety Evaluation Re Inservice Testing Plan Request for Relief RR-5 Component Cooling Water & Safety Injection Sys Containment Isolation Check Valve Closure Test Frequency ML20210C2111999-07-21021 July 1999 Forwards Insp Repts 50-498/99-13 & 50-499/99-13 on 990516-0626.Two Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20209H9231999-07-16016 July 1999 Discusses South Texas Project,Units 1 & 2 Updated Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity. Staff Revised Info for Plant in Rvid & Being Released as Rvid Version 2 ML20207H6261999-07-0808 July 1999 Responds to Re 2nd 10 Yr Interval ISI Program Plan Request to Use ASME Section XI Code Case N-546, Alternative Requirements for Qualification of VT-2 Exam Personnel,Section Xi,Division 1.Forwards SE ML20195J6731999-06-17017 June 1999 Responds to Re Request for Relief from ASME Code, Section Xi,Requirement to Perform VT-1 Visual Exam on Accessible Surfaces of RPV Flange Inserts (Bushings). Safety Evaluation Encl ML20195F7561999-06-10010 June 1999 Forwards Insp Repts 50-498/99-11 & 50-499/99-11 on 990404-0515 at South Texas Project Electric Generating Station,Units 1 & 2.No Violations Were Identified ML20207H0031999-06-0909 June 1999 Discusses 990419 Meeting in Region IV Ofc Re South Texas Project EP Program Status,Including Initiatives in EP Program,Future Revs to EP & Dept Performance Indicators. Meeting Attendance List & Licensee Presentation Encl ML20195G3241999-06-0909 June 1999 Ack Receipt of Re Changes to Plant Emergency Plan Change Notice 18-2.No Violations of 10CFR50.54(q) Were Identified ML20207D7371999-05-28028 May 1999 Discusses Re Process for Reclassification of non- Risk Significant Components.Forwards Concerns & Cautions for Consideration Based on Limited Review of Reclassification Process Overview That Was Provided IR 05000498/19980151999-05-28028 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/98-15 & 50-499/98-15.Corrective Actions Reviewed & Found to Be Responsive to Issues Raised ML20207E1961999-05-25025 May 1999 Forwards Insp Repts 50-498/99-09 & 50-499/99-09 on 990503-06.No Violations Noted.Primary Focus of Insp to Review Operational Status of Emergency Preparedness Program ML20207A8771999-05-25025 May 1999 Forwards RAI Re Licensee 960213 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant,Units 1 & 2.Response Requested within 120 Days from Date of Ltr IR 05000498/19990061999-05-12012 May 1999 Submits Corrected First Page of Cover Ltr Re Insp Repts 50-498/99-06 & 50-499/99-06 Conducted on 990221-0403.Subj Line Was Corrected ML20206S3201999-05-12012 May 1999 Forwards Corrected First Page of Cover Ltr,Which Forwarded Insp Repts 50-498/99-06 & 50-499/99-06,issued on 990505. Subj Line Indicated on NOV Was Incorrect ML20206N5481999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ra Gramm Will Be Section Chief for South Texas Project.Organization Chart Encl ML20206J4321999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key Encl for Info.Without Encl ML20206J4211999-05-0606 May 1999 Ack Receipt of in Response to & Insp Repts 50-498/99-04 & 50-499/99-04,confirming Commitments as Stated in 990225 Exit Meeting ML20206H6201999-05-0505 May 1999 Forwards Insp Repts 50-498/99-06 & 50-499/99-06 on 990221- 0403.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206H3811999-05-0505 May 1999 Responds to STP Nuclear Operating Co Which Provided Update to TS Bases Pages B 3/4 2-6.Revised TS Bases B 3/4 2-6 That NRC Staff Will Use to Update Copy of STP Bases Encl ML20206H2001999-05-0404 May 1999 Forwards Exemption from Requirements of 10CFR50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation ML20206B6091999-04-22022 April 1999 Forwards Insp Repts 50-498/99-10 & 50-499/99-10 on 990405-09.No Violations Noted ML20206B3281999-04-22022 April 1999 Forwards Insp Repts 50-498/99-07 & 50-499/99-07 on 990405- 09.Insp Focused on Radiological Controls in Place During Unit Refueling Outage.Violations Identified Involving Failure to Follow Radiation Work Permit Instructions ML20205Q8151999-04-16016 April 1999 Forwards Request for Addl Info Re Proposed Amends on Operator Action for small-break-LOCA,dtd 980728.Response Requested within 45 Days of Ltr Date ML20205P5821999-04-15015 April 1999 Advises That Version of Application & Affidavit Dtd 990127, Executed by Ha Sepp,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended 1999-09-09
[Table view] |
Text
-
. v MY 19 %
Docket Nos: 50 -498 and 50 -499 Mr. J. H. Goldberg Group Vice President - Nuclear Houston I.ighting and Power Company Post Office Box 1700 Fouston, Texas 77001
Dear Mr. Goldberg:
SUBJECT:
SECOND AUDIT OF TFE SOUTH TEXAS PROJECT (STP)
QUAI.IFIED DISPLAY PROCESSING SYSTEM (QDPS).
Enclosed are the results of the second audit conducted by the staff of the QDPS at the Westinghouse facilities in Monroeville, Pa. Based on our audit of the design process and of the verification and validation activities for the Plant Safety Monitoring System (PSMS) and Qualified Control System within the QDPS, the staff concludes that it is generally acceptable to continue the design and manufacture of these systems and to execute the verification and validation plan. However, this acceptance is conditional on having a validation plan sufficiently broad in scope to address any discrepancies in the design process and to compensate for the lack of independent, formal design verification.
The staff's review of the validation plan will be conducted at the third audit In addition, we have identified issues on software maintenance and documentation, which will also be audited.
The tnird audit in this series in tentatively scheduled for the third week in June, 1986. Please contact me at (301) 492 -7272 if you have any questions.
N. Prasad Kadambi, Project Manager PWR Project Directorate No.
Division of PWR I.icensing-A
Enclosure:
- 1. Audit Report, Houston I.ighting & Power Company Qualified Display Processing System
- 2. Attendence I.ist cc: F. Rosa (EICSB)
Distribution
. Docket J11es PD#5 R/F EJordan PKadambi NRC PDR TNovak JPartlow ACRS(10) 1.ocal PDR OE!.D B. Grimes NRushbrook PD#5 PKadaa i (f V IR: #5 onan 5 /86 5 6 8605280182ggo ADOCK 98 PDR PDR A
i M
' UNITED STATES es 3 [g), t j NUCLEAR REGULATORY COMMISSION WASHINGTON, O C. 20555 f....h.-
une as Docket Nos: 50 -498 and 50 -499 Mr. J. P. Goldberg Group Vice Dresident - Nuclear Houston t.ighting and Power Company Post Office Box 1700 Pouston, Texas 77001
Dear Mr. Goldberg:
SUBJECT:
SECOND AUDIT OF THE SOUTP TEXAS PROJECT (STP)
QUAT.IFIED DISPl.AY PROCESSING SYSTEM (QDPS).
Enclosed are the results of the second audit conducted by the staff of the QDPE at the Westinghouse facilities in Monroeville, Pa. Based on our audit of the design process and of the verification and validation activities for the Plant Safety Monitoring System (PSMS) and Qualified Control System within the QDPS, the staff concludes that it is generally acceptable to continue the design and manufacture of these systems and to execute the verification and validation plan. However, this acceptance is conditional on having a validation plan sufficiently broad in scope to address any discrepancies in the design process and to compensate for the lack of independent, formal design verification.
The staff's review of the validation plan will be conducted at the third audit In addition, we have identified issues on software maintenance and documentation, which will also be audited.
The third audit in this series in tentatively scheduled for the third week in June, 1986. Please contact me at (301) 492 -7272 if you have any questions, f
,. 4 . cdl. .
N. Prasad Kadambi, Project Manager PWR Project Directorate No.
Division of PWR Licensing-A
Enclosure:
- 1. Audit Report, Pouston I.ighting & Power Company Qualified Display Processing System
- 2. Attendence f.ist cc: F. Rosa (EICSB) 4
. _ . . . . . -.;_:.a. .
Mr. J. F. Goldberg Fouston lighting and Power Company South Texas Project CC' Brian Berwick, Esq. Resident Inspector / South Texas Assistant Attorney General Project Environmental Protection Division c/o U.S. Nuclear Regulatory Commission P. O. Box 12548 P. O. Box 910 Capitol Station Bay City, Texas 77414 Austin, Texas 78711 Mr. Jonathan Davis Mr. J. T. Westermeir Assistant City Attorney Manager, South Texas Project City of Austin Fcuston 1.ighting and Power Company P. O. Box 1088 P. O. Box 1700 Austin, Texas 78767 Fouston, Texas 77001 Ms. Pat Coy Mr. F. L. Peterson Citizens Concerned About Nuclear Mr. G. Pokorny Power City of Austin 5106 Casa Oro P. O. Box 1088 San Antonio, Texas 78233 Austin, Texas 78767 Mr. Mark R. Wisenberg Mr. J. B. Poston Manager, Nuclear licensing Mr. A. Von Rosenberg Pouston lighting and Power Company City Public Service Boad P. O. Box 1700 -
P. O. Box 1771 Fouston, Texas 77001 San Antonio, Texas 78296 Mr. Charles Falligan Jack R. Newman, Esq. Mr. Burton L. Lex Newman & Holtzinger, P.C. Bechtel Corporation 1615 1. Street, NW P. O. Box 2166 Washington, D.C. 20036 Fouston, Texas 77001 Melbert Schwartz, Jr., Esq. Mr. E. R. Brooks Baker & Botts Mr. R. L. Range One Shell Plaza Central Power and light Company Fouston, Texas 77002 P. O. Box 2122 Corpus Christi, Texas 78403 Mrs. Peggy Buchorn Executive Director Citizens for Equitable Utilities, Inc.
Route 1, Box 1684 Brazoria, Texas 77422
. -- . c ,
. l Houston lighting & Power Company South Texas Project l i
l CC:
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 <
Mr. I.anny Sinkin, Counsel for Intervenor Citizens Concerned about Nuclear Power, Inc.
Christic Institute 1324 North Capitol Street Washington, D.C. 20002 licensing Representative Pouston lighting and Power Company Suite 1309 7910 Woodmont Avenue Bethesda, Maryland 20814 i a
~,
ENCLOSURE 1 SECOND AUDIT REPORT HOUSTON LIGHTING AND POWER COMPANY QUALIFIED DISPLAY PROCESSING SYSTEM
- 1. BACKGROUND The Houston Lighting and Power Company (HL&P) is developing a microcomputer based system, which will perform functions that will directly impact upon the safe operation of its South Texas Project (STP). The STP is a dual 1250 MW Westinghouse Pressurized Water Reactor (PWR) Nuclear Generating Station, which is currently scheduled for completion and licensing by June 1987.
The microcomputer based system is being designed by Westinghouse and is called the Qualified Display Processing System (QDPS). This system is described in the applicant' FSAR and it is being designed to perform the following functions:
Data acquisition, processing, and qualified (Class 1E) display for Post Accident Monitoring, 4
Data acquisition, display, and analog control for Safe Shutdown and to address separation / isolation concerns for a postulated Control Room / Relay Room fire, Data acquisition and digital processing of steam generator water level signals and primary coolant system hot leg temperature signals and transmission of these processed signals for use by the Reactor Trip System.
The staff's review of the QDPS began with an audit of the Verification and Validation Plan, which was conducted during August 26-29, 1985. The staff's
, audit results and recommendations are presented in Reference 1.
i .
I j a 1
In preparation for a second staff audit on the QDPS, the applicant requested a meeting with the staff, which was held on March 18, 1986, at NRC Headquarters in Bethesda, Maryland. During'the meeting, the applicant identified and discussed a functional requirements matrix, which had been prepared for the j design. Also, the applicant identified the design documents that would be-l available for staff audit, including procedure and module listings within the
}
software. Based on the large bulk of design information available, the staff decided to review a thread of infonnation (described later) within the design and we informed the applicant and Westinghouse's personnel of this decision.
The staff's second audit of the QDPS was conducted during March 24-27, 1986, at Westinghouse Electric Corporation's Nuclear Facilities, located in Monroeville, Pennsylvania. The audit was conducted by Mr. J. L. Mauck, Mr. L. Beltracchi, and Mr. J. Joyce of the NRC Staff. Enclosure 2 contains j a list of personnel at the audit.
4 II. SCOPE OF AUDIT
\ l The purpose of this audit was to conduct a functional review of the design process for the Plant Safety Monitoring System (PSMS) and the Qualified 1 Control (Class 1E) System within the QDPS. The PSMS is a gas plasma type of I
_ display system, which serves as an operator interface in response to Regulatory Guide 1.97 requirements on post accident monitoring capabilities.
Data for the following functions may be monitored from the system:
- 1) subcriticality, 2) reactor core cooling, 2) heat sink maintenance,
- 4) reactor coolant system integrity, 5) containment environment, and
- 6) reactor coolant system inventory. Also, trend data for process variables and process variable versus process variable, such as pressure versus temperature type of plots, are available within the library of display formats in the display system. A human factors review of the display formats was not performed.
l The Qualified Control System function within the QDPS performs valve control including: (1) closed loop control and position indication for the steam generator power-operated relief valves, (2) contact output signals for automatic control and position indication of auxiliary feedwater control valves within the upper and lower flow limits, (3) open-loop control and .
position indication for the reactor vessel heat vent valves, and (4) closed loop control and position indication for essential cooling water flow control valves to safety related HVAC chillers.
During the audit, a period of time was spent evaluating the applicants and Westinghouse's response to open issues identified during our first audit (Ref. 1) of the the QDPS. Also, the staff provided clarification on some of these issues in response to questions from Westinghouse personnel.
III. AUDIT METHOD To conduct the audit, the staff reviewed a thread of design information to evaluate the PSMS and the Qualified Control System. Specifically, a sensor signal was selected and the signal was then followed from the sensor through the hardware and software components of the QDPS until an interface with another system / component was reached. Design documentation in the form of wiring diagrams, technical data sheets, and computer program listings were used to trace the signal and evaluate the operations upon it. Furthermore, the staff requested Westinghouse personnel to identify points in the thread where design verification and validation (V&V) activities had occurred or were planned. At identified points where V&V activities had occurred, the staff requested the results of the activities in order to evaluate the effectiveness of the design process and the independent design verification.
The above described audit method was used to trace a flow transmitter's signal through the Qualified Control System function within the QDPS. This signal measured auxiliary feedwater flow. The review of this thread was terminated
at the interface of the QDPS and the auxiliary feedwater flow control valves.
A pressure transmitter's signal was traced through the PSMS function within the QDPS. This signal measured containment pressure. The review of this signal was terminated at the display surface (plasma display) at the point where the value for pressure was displayed. The results from our audit, which follow next, serve as the basis of the staff's evaluation of the design used to develop the Qualified Control System and Plant Safety Monitoring System's functions within the QDPS.
IV. AUDIT RESULTS j
The first patt of the audit was dedicated to the resolution of open review issues identified in our first audit report (Ref. 1). The second part of the audit concentrated on the review of the three major sub-systems within the QDPS by means of the thread concept. This concept allowed the staff to evaluate the effectiveness of the design process and the V&V program.
A. Open Issue and Clarification from First Audit
- 1. Audit Trial As stated in our first audit report, we noted that the design process from
- functional requirements through implementation was difficult to follow.
On March 18, 1986, during a meeting in Bethesda, Md. the applicant presented a Functional Requirements Matrix Document to address this concern. Based on this meeting, the second audit, and our evaluation of the matrix, we conclude that the matrix identified a structure of the design from the functional requirements document down to the software code. We were successful in the use of this matrix to demonstrate decomposition from the functional requirements to the design specifications. Therefore, this issue is resolved.
i
- 2. Question of Independent Design Verification As identified in our first audit report, we noted the lack of independent design verification within the design process. It is our engineering judgment that the validation plan should be sufficiently broad in scope to address discrepancies in the design process and to account for the lack of independent, formal design verification. Therefore, based on this judgment, the question of independent design verification within the design process has been shifted to the validation plan, which will be evaluated during the third audit.
- 3. Software Criticality During the first audit, our consultant (SoHar) was concerned that the V&V process did not allocate resources proportional to safety functions and task performed by the software. During the second audit, we were informed that Westinghouse went to the same (stringent) level of V&V effort on all software units because designers were unable to justify lack of interactions between units. We conclude this is a conservative approach and acceptable to the staff.
- 4. Clarification of Physical Media One of the open items in our consultants (SoHar) audit report was the verification of the physical media that represents the program. The applicant and Westinghouse requested clarification / interpretation of this item. The verification of physical media means those activities performed to ensure that the burned in programmable read only memory (PROM) contains the authorized program (i.e., security and safeguard measures). The staff plans to evaluate these verification activities at a future audit.
l
- 5. Other Open Items The following items were also noted in our first audit report, but were not addressed at this time. These items will be addressed during the third or fourth audit:
- a. Software maintenance practices prior to and during operational use,
- b. User and maintenance documents.
- c. Reliability analysis,
- d. Verification of the program listing.
B. Results from Second Audit As mentioned above, the thread concept was used as a method to audit three sub-systems of the QDPS (see Figure 1). This concept was effective
, during the review of RESAR-414. .This audit technique allows the staff to evaluate the effectiveness of the design process and the independent design verification.
- 1. Steam Generator Water Level Compensation System (SGWCS)
For the SGWCS (Figure 2.0), we started tracing the signal at the sensor (RTD-TE 571) and continued up to the interface with the NSSS 7300
~ protection cabinets (Figure 3.0). The hardware walk through began at the input to the signal conditioner card via pins, jacks, cable, card edge connectors, and electronic devices terminating at the output of the A/D converter. The software walk through began at the output of the A/D converter and continued through modules and procedures, which processed the signal,-and terminated at the D/A converter. The analog signal then passed through the signal conditioner card that interfaced with the 7300 protection cabinets. !
l l
l 4
e n q- y -,,-- ,y,g-- r-- .-g -y---,
=
We were able to successfully trace the temperature signal through the hardware and software logic, which converts the signal to engineering units. During this process, we noted the utility of the functional requirements matrix in following the thread through the softward.
- 2. Qualified Control System-AFW Throttle Valve Control Loop The second sub-system in which we used the thread concept was the Class-1E control system (Figure 4.0). As stated above, there are four control loops within this subsystem. The auxiliary feedwater (AFW) throttle valve control loop was chosen as part of the thread (Figure 5.0).
We started from the flow transmitter (FT-7525) and traced the signal through signal conditioning card, A/D converter, software modules and procedures, which process the signal. The software algorithms generated an output signal to the D/A converter for the valve position. We then followed this analog signal to the valve controller. During this process, we requested Westinghouse to identify and present independent design verification activities for our evaluation.
We assessed the verification activities for a procedure, which performed a square root function. We noted that the scope of the verification conformed to the V&V plan and contained detail documentation (i.e.,
trouble reports). We evaluated the trouble reports and their resolution and concluded they were satisfactorily addressed.
- 3. Plant Safety Monitoring System (PSMS)
The third and final sub-system we reviewed was the PSMS (Figure 6.0). We traced the signal from the containment extended range pressure transmitter (PT-9759) and followed the signal up to the plasma display (Figure 7.0).
.. : ~
We were successful in tracing the signal through the hardware, the software, and to the surface of the plasma display. As part of the software walk through, we randomly selected a requirement from the PSMS functional requirements matrix. We attempted to trace attributes of the functional requirements to the software design specifications and were unable to do so. From this exercise, we concluded that the decomposition from the functional requirements to the design specification maybe incomplete. We also made this observation during the first audit.
Therefore, we repeat our recommendation from the first audit; the validation plan be sufficiently broad in scope to address any discrepancy in the design process and account for lack of independent, formal design verification.
V. CHAPTER 7 FSAR REVIEW The following review topics have been highlighted by the staff for subsequent review during one of the remaining QDPS audits or during additional design review meetings, which would be scheduled at a later date.
Interface with alternate remote shutdown capability.
Isolation devices (interface with non Class IE systems).
- Interface with Class IE systems.
Testability (R.G. 1.22, 1.118 and IEEE-338) (including proposed Technical Specifications).
Bypassed and Inoperable Status Indication (R.G.1.47).
EMI Susceptibility.
R.G. 1.75 Separation of redundant safety trains within QDPS.
Manual initiation methods.
General compliance with IEEE-279 (e.g., single failure criterion, resetcapability).
b
VI. FUTURE AUDIT ISSUES As stated in the first audit report, we recommend a total of four audits to assess the QDPS. We have completed two audits. The third and fourth audits will address the following:
An evaluation audit of the Validation Plan; An evaluation audit of the test process and test results; and An evaluation of the open items identified in IV.A.4 and 5 above.
We recommend these audits be conducted at Westinghouse's facilities because design and test documentation will be required.
VII. CONCLUSIONS AND RECOMMENDATIONS Based on our audit of the design process and the verification and validation plan for the PSMS and Qualified Control System within the QDPS, the staff concludes that it is generally acceptable for the applicant to continue the design and manufacture of this system and to continue to execute the verification and validation plan. However, as stated in Item IV.B.3 above, this acceptance is conditional to having a validation plan sufficiently broad in scope to address any discrepancies in the design process and account for the lack of independent, formal design verification. This means that the validation plan should include a technique to demonstrate completeness between Functional Requirements and Software Design Specifications that were turned over to the validation team. The staff's review of the validation plan is the subject of the next audit. In addition, we have identified other issues
- da" Item IV.A.4 and 5, that will also be addressed during the third and rth audit of QDPS.
References:
- 1. Letter from N. P. Kadambi, NRC to J. H. Goldberg, Houston Lighting and Power Company,
Subject:
Audit Report on the QDPS at South Texas Project, Units 1 and 2, dated January 30, 1986.
e
-- ~~ ' '
r !
- ' l i .
l QUALIFIED DISPLAY PROCESSING SYSTEM (QDPS)
QDPS
~
STEAM GENERATOR PLANT SAFETY CONTROL WATER LEVEL MONITORING (CLASS 1E) COMPENSATION
~ SYSTEM (PSMS)
SYSTEM (SGWLCS)
.~ (PROTECTION) c Figure 1.0 t
4 e ,w n-e--we-e em.,.,n, . , - - - - , . - -en -g - - - , . _ , . -g- , , , - - , -nn,, - - - , , --, -r --~,,,---, -,-,-re,,., - , . , - - .-e,- -w-,,-e,ey-- -p en-,,-
i-
~
.~
QUALIFIED DISPLAY PROCESSING SY' STEM (ODPS)
FLOW DIAGRAM ODPS 1 T
~ CONTROL IlfYE COMo L EL PLANT SAFETY MONITORING (CLASS IE)
SYSTEu 5 OCS TEM (PROTECTION) )
SYfO!jP5MS)
OR)
[
CONTROL LOOP DATA LINK MAN-WACHINE IN E CE
~
"idirtJNE' PORTABLE TERMINAL F0t9 E L R J
ODPS NSSS 7300 To M State i Auxiliary Process Cattnet APC-A2 Protection Cabinet I syst (SSP
.. s
~
! 4.sounA Signal Control Digital Signal 4.scinA Signal o, ,,, Matsis HI M j Cond. Loop , to Cond. j Cond. j ~ L ,,g l y input - Processor ** - o- Analog -* Output . : Input . : :
j
- LT-571 PC Card (CLP)
I(x)
Converter (D/A)
PC Card compenoeged PC Card Loves
]
Turbine Trip Signal N Analog L N h Nat:4s M Lo '
Data
Nd to I k b Reactor
! fteelesence Signal f B (DLH) nsau -
j j Cond. U ,
1 TE - Input '
S ,
lTE-571A -ODPS- R8 -ODPS- RS fleentonce Man APC 422 422 l TE-571 hd %
Inter ce (nea)
Unit (RPU) 2 Proc unsre (DPLfe) 1 i -
a i
e APC-Al e
< e I 4 l PortaMe ,
1 MMI j -
Tarnunal i
I v
I STEAM OENERATOR WATER LEVEL COMPENSAh0N SYSTEM (SGWLCS) CHANNEL Figure 3.0 '
3
', . 1 9
OUALIFIED DISPLAY. PROCESSING SYSTEM '
(ODPS)
FLOW DIAGRAM ODPS .
. STEAM GENERATOR PLANT SAFETY CU TROL WATER LEVEL WONITORING C P S "
(CLASS IE) Sy { CS)
SY P 5)
CONTROL LOOP CESSOR 2 -- CLP) -
l
! DATA LINK HANDLER (DLH) i a
, WAN-WACHINE 4
INTERFACE f
(WWI) -
WAN-WACHINE INTERF. ACE PORTABLE
.)" TERMINAL
- Fioure 4.0
- e. . ..
l i
l 4-20mA Signal AnaloQ Control j Cond. to Loop i : Input -* Digital * +-*
y Processor PC Card Converter (CLP)
FT-7525 (A/D)
M M i RS232 U Data ,
--* : To PSMS RPU Ha er (DLH) l U Man /
! Machine Portable
- S .-. Interf ace --------------+ MMI ,
i Processor Terminel '
l (MMO Sign I '
contact : Valve Control -
Digital Digital t High Limit B/S to input / -
PC ard -
Analog *
- Output Converter (1/0) CO ; Valve Control-(D/A) Low Lknit B/S Signal pO-10V Cond.
Analog A_ Flow
) "'
indication
_ Output PC Card APC
. i AFW THROTTLE VALVE CONTROL LOOP BLOCK DIAGRAM Figure 5.0 4
i t
I I
QUALIFIED DISPLAY PROCESSING SYSTEM (QDPS)
FLOW DIAGRAM l
QDPS
, STEAM GENERATOR CONTROL WATER LEVEL PUNT MFETY (CLASS 1E) COMPENSATION MONITORING
-~
SYSTEM (SGWLCS) SYSTEM (PSMS)
. (PROTECTIONI ,_
~
REMOTE PROCESSING' UNIT (RPU)
DATABASE PROCESSING 1
- UNIT (DPU)
DISPLAY MODULE k
Figure 6.0
w PLASMA DISPLAY QUAL.
PAMS CNTMT PT9759 Z 4-20 mA h > APC DI D/L
> DPU A D/L
> DISPLAY 3
~
s
' sD/L f 1
sD/L im
' s e' P. 7 s ! ID/L
\ ~
N OI
' s , D/L,be' .
s i \
,e \
DPU C I
DA' f ' 's
~ q RECORDER g i PR '
I DEMUX I _ _ _ _ _ _ _ y\9759 f, I
s-i_ _ ___ _ _I SIGNAL PATH FOR PT9759 (EXTENDED RANGE CONTAINMENT PRE Figure 7.0 s
, 'r -
ENCLOSURE 2 QDPS AUDIT (MARCH 24,1986)
Attendence List Name Organization Iris Tennenbaum W PCA Chuck Carl W Mgr. PCA Glenn Lang W Licensing Mary Moreton BEC Control Systems Leo Beltrechi NRC/PWR-B/PEICSB Joseph Joyce NRC/DSR0/RSIB Jerry Mauck NRC/PWR-A/EICSB
~
Jack N. Bailey HL&P Engineering Tom H. Crawford HL&P I&C Engineering Yvonne Williams BEC Control Systems Carl Vernon W STP Licensing Team John R. Smith W/I&C/Dignostic & Monitor Syst. Div.
Jay Amin BEC W. R. Spezialetti W Licensing R. J. Contratto W I&C Licensing Paul H. Mathewes, Jr. MASI Gary B. Glisan MASI W. W. Brotherton W PCA D. P. Adomaitis W I&CAE 9
9 QDPS AUDIT (MARCH 25,1986)
Attendence List .
Name Organization Iris Tennenbaum W PCA Chuck Corl W Mgr. PCA Glenn Lang W Licensing Mary Moreton -
BEC Control Systems Leo Beltrcchi NRC/PWR-B/PEICSB Joseph Joyce NRC/DSR0/RSIB Jerry Mauck NRC/PWR-A/EICSB Jack N. Bailey HL&P Engineering Tom H. Crawford HL&P I&C Engineering '
Yvonne Williams BEC Control Systems Carl Vernon W STP Licensing Team John R. Smith W/I&C/Dignostic & Monitor Syst. Div.
D. Adomaitis W I&CAE Jay Amin BEC F. R. Hughes W I&C Paul H. Mathewes, Jr. MASI Gary B. Glisan MASI W. W. Brotherton W PCA G. W. Hadden W Pyh.
k l
. t e QDPS AUDIT (MARCH 26,1986)
Attendence List Name Organization Chuck Corl W Mgr. PCA Glenn Lang W Licensing Mary Moreton BEC Control Systems Leo Beltrechi NRC/PWR-B/PEICSB -
Joseph Joyce -
-NRC/DSR0/RSIB Jerry Mauck , NRC/PWR-A/EICSB Tom H. Crawford HL&P I&C Engineering Yvonne Williams BEC Control Systems Carl Vernon W STP Licensing Team John R. Smith W/I&C/Dignostic & Monitor Syst. Div.
Jay Amin BEC Paul H. Mathewes, Jr. MASI Gary B. Glisan MASI D. P. Adomaitis W I&CAE E
o 4
6
.: ... - = . a . : . w. w. - :
.. . r e j
l l
QDPS AUDIT (MARCH 27, 1986)
Attendence List Name Organization Iris Tennenbaum W PCA Chuck Corl W Mgr. PCA Glenn Lang W Licensing Mary Moreton BEC Control Systems Leo Beltrechi NRC/PWR-B/PEICSB
~
Joseph Joyce NRC/DSR0/RSIB Jack N. Bailey HL&P Engineering Fred Twogoud W Drvs. Mgr.
Tom H. Crawford HL&P I&C Engineering Yvonne Williams BEC Control Systems N P. Kadambi NRC/NRR/PD#5 Carl Vernon W STP Licensing Team John R. Smith W/I&C/Dignostic & Monitor Syst. Div.
Jay Amin BEC W. R. Spezialetti W Licensing
- R. J. Contratto W I&C Licensing Paul H. Mathewes, Jr. MASI Gary B. Glisan MASI ,
N. J. Musicante W I&C W. W. Brotherton W PCA D. P. Adomaitis W I&CAE J. B. Wacio W I&C T. A. Pike CTG l
i
, . _ . , _ . . - . . . _. , , .