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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] |
See also: IR 05000498/1990028
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NW 151990
Docket Nos. 50-498/90-28
50-499/90-28
License Nos. NPF-76
NPF-80
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Houston Lighting & Power Company .
ATTN: Donald P. Hall, Group
Vice President, Nuclear
P.O. Box 1700
Houston, Texas 77251
Gentlemen:
Thank you for your letter of October 17, 1990, in response to our letter i
and Notice of Violation dated September 18, 1990. We have reviewed your- reply
and find it responsive to the concerns raised in our Notice of Violation
(498/9028-01;499/9028-02). We will- review the implementation of your.
corrective actions during a future inspection to determine that full compliance
has been achieved and will be maintained.
Sincerely,.
/5/
. Samuel J.. Collins, Director
Division of Reactor. Projects ,
cc:
Houston Lighting & Power Company
ATTN: M. A. McBurnett, Manager
Operations Support Licensing
P.O. Box 289
Wadsworth, Texas 77483
City of. Austin- ,
Electric Utility Department
ATTN: J. C. Lanier/M. B. Lee
P.O. Box 1088'
Austin, Texas 78767
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RIV:DRP/D M C:DRP/D D:DRP Ub Y ..
WBJones;df p ATHowell g JCollins {
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City Public Service Board
ATTN: R. J. Costello/M. T. Hardt
P.O. Box 1771-
San Antonio, Texas 78296
Newman & Holtzinger, P. C.
ATTN: Jack R. Newman, Esq.- 1
1615 L Street, NW >
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Washington, D.C. 20036 !
Central Power and Light Company , -!
ATTN: R. P. Verret/D. E. Ward t
P.O. Box 2121
l- . Corpus Christi, Texas 78403
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INP0
Records Center ' .
4
1100_ Circle 75 Parkway .
Atlanta, Georgia- 30339-3064 ,
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Mr. Joseph M. Hendrie
50 Bellport Lane.
Bellport, New York 11713
Bureau of Radiation Control *
State of Texas
1101 West 49th Street
Austin, Texas 78756
i- Judge, Matagorda County
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Matagorda County Courthouse
1700 Seventh. Street
. Bay City, Texas 77414
Licensing Representative
Houston Lighting & Power Company
Suite 610
Three Metro Center
. Bethesda, Maryland 20814
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Houston- Lighting & Power :Conpany :
ATTN: Rufus S. Scott, Associate
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General Counsel
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P.O. Box 61867
Houston, Texas ~77208
bec to DMB (IE01) w/ licensee ltr.
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bec distrib. by RIV w/ licensee 1tr.:
R. D. Martin Resident Inspector
DRP SectionChief(DRP/D) ;,
DRS MIS System
DRSS-FRPS Lisa Shea, RM/ALF ,
RIV File R. Bachmann, OGC
RSTS Operator Project Engineer (DRP/D).
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October 17, 1990
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Filo No.: C02 04-
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10CFR50.73
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U. S. Nuclear Regulatory Commission
Attention: Document Control Desk
Vashington, DC 20555 !
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South Texas Project Electric Generating Station
-Unit 1
Response to Notice of Violations 9028 01 Land 19028 02
Failure to Follow Procedures.'for . Independent
Verification and Failure to Provide-Adecuate Accentance Criteria
Houston Lighting & Power has. reviewed the Notices of Violations issued j
as a result of NRC Inspection ' Report 90 028 dated September.18,1990, and. !
l submits the attached responses,
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Notice of Violation 9028-01 occurred during the post trip recovery f
. effort for Unit 1 LER 90 006.. The response for' this violation is completely - '
covered in the attached LER 90 006 regarding a manual reactor trip due:to full' )
closure of'a WIV -during partial.' stroke testing. l
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-If you should have any questions on this-matter, please contact l
Mr. A. K. Khosla-at (512) 972 7579 or myself at (512) 972 8530. '
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M. A. McBurnett
Manager.
Nuclear. Licensing
AKK/sgs
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Attachment: Reply to Notices of Violations'9028 01.and 9028 02
IIR 90 006 (South Texas, Unit 1)
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ST.HL AE 3596
llouston Lighting & Power Compan)- File No.:002.04
. South Text. Proj,ect Electric Generat og Stat.ion Page 2
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cc:
Regional Administrator, Region IV Rufus=S.= Scott
Nuclear Regulatory Commission Associate General Counsel ('
611 Ryan Plaza Drive, Suite 1000 ' Houston Lighting & Power Company .
Arlington, TX 76011 P. O. Boi 61867
Houston, TX 77208
Coorge Dick, Project Manager
U.S. Nuclear Regulatory Commission INPO ;
Washington, DC 20555 Records Center v
1100 circle 75 Parkway
J. I. Tapia Atlanta, GA 30339 3064
Senior Resident Inspector ..
,
c/o U. S. Nuclear Regulatory Dr. Joseph M.L Hendrie:
Commission 50 Bellport Lane-
P. O. Box 910~ Bellport, NY .11713
Bay City,1D( 77414
D. K. Lacker ,
J. R. Newman, Esquire Bureau of Radiation Control
Newman & Holtzinger, P.C. Texas Department of Health
1615 L Street, N.W. 1100 West 49th Street
Washington, DC -20036. Austin, TX 78756 3189
R. P. Verret/D. E. Ward
Central Power 6 Light Company
P. O. Box 2121
Corpus Christi, TX 78403
J. C. Lanier/M. B. Lee
City of Austin
Electric Utility Department
P.O. Box 1088
Austin, TX 78767
R. J. Costello/M. T. Hardt
City Public Service Board
P. O. Box 1771
San Antonio, TX 78296
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-Revised 10/08/90
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Attachment
ST.HL.AE.3596 '
Page 1 of 3
j 1. Statement if Violations:
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1. Failure to rollow Procedures for indenendent verificarica
10 CPR Part $0, Appendix B Criterion V, requires, in part, that *
activities affecting quality be accomplished in accordance with
- documented instructions,
,
i Plant Procedure 1 PSP 03. AF.0001, Revision 6, " Auxiliary Feedwater
Pump 11 Inservice Test,' Step 5.13,1, states, 'CLost and LOCK Test
Line Isolation Valve AF0040 and initini Data sheet ( 2),' and Step
5.13.2, states 'As a (sic) independent verification have a second
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individual verify Ar0040 is CLOSED And LOCKED and initial .Seta
Sheet ( 2). >
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Plant Procedure OPOP03 20 0004, Revision 11, ' Plant Conduct of
Operations,* Step 4.4.11, requires that independent verifications
shall be performed as prescribed by approved procedures or
' ,atructions in accordance with OPCP03.ZA.0010, " Plant Procedure
Compliance, Implementation, and Reviews '
Plant Procedure OPCP03.ZA.0010, Revision 11, * Plant Procedure
Compliance Implementation, Review,' Step 3.3.2.1, states that the
act v; performing the independent verificatio14 must be completely
separate and independent of the initial alignment, installation, or
verification.
Contrary to the above, on July 26, 1990, Steps 5.13.1 and 5.13.2 of
Plant Procedure 1 PSP 03 AF 0001 Revision 6, " Auxiliary Teedwater
Pump 11 Inservice Test," were performed concurrently and were,
therefore, not completely separate and independent. This resulted
in a failure to detect that Test Line Isolation Valve AF0040 was
erroneously aligned in a locked open position. This error was '
discovered following a reactor trip on August 6, 1970, when
auxiliary feedwater from Auxiliary Feedwater Pump No.11 was
circulated back to the auxiliary feedwater storage tank through the t
locked open valve instead 9f adding water to steam Generator A as
designed.
This is a Severity Level IV violation. (Supplement I) (498/9028 01)
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ST.HL. AE. 3596
Page 2 of 3
2. Failure to Prqvide Adecuate Acceptance Criteria
10 CFR Part 50, Appendix B, Criterion V requires, in rett, that !
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procedures include appropriate acceptance criteria for determining
that important activities have been satisfactorily accomplished, i
South Texas Project Technical Specifications, paragraph 6.8.1.a.
requires that procedures for activities identified in Appendix A of
Regulatory cuide 1.33, Revision 2, February 1978, be established,
- implemented, and maintained. Paragraph 3 to Regulatory Guide 1.33
requires that instructions for energizing, filling, venting,
draining, startup, shutdown, and changing modr.s of operation be
prepared for the chemical and volume control system (including
letdovn/ purification system).
Cor.trary to the above, on August 6. 1990, neither Operations
Procedure 1 POP 02.CV.0004, ' Chemical Voluue sad Control System
Subsystem,' Revision 8, or any administrativi procedure contained
adequate acceptance criteria for determining hat the activities to
place a mixed bed desineraliser in service had been satisfactorily
accomplished.
This is a Severity Level IV violation. (Supplement 1) (498/9028 02)
II. Houston Limhting & Power Position:
1. HL&P concurs that this violation occurred and attaches LER 90 006 in
response to this violation.
2. HL&P concurs that this violation occurred.
I III. Reason for Violation ,
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1. See attached LF.R 90 006.
, 2. The cause of this event was the procedure for placing the
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desineraliser in service did not requite a sample or provide an
acceptance criteria for boron concentration prior to demineralizer
use. Additionally, the procedure for borating the desineralizer was
also less than adequate,
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ST.HL.AE 3596
Page 3 of 3 l
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IV. Corrective Act!P.nt!
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1. See attached 12R 90 006, corrective actions 4 8. ,
2a. The procedure for placing domineralizers ir service has been revised
to require domineralizer sampling and to specify acceptance criteria
when placing a demineralizer in service, j
b. The procedure for borating domineralizers has been changed to ,
require the domineralizer outlet isolation valve to be closed for
the demineralizer that is not being flushed for sampling. This will ;
assure that only one demineralizer is flushed and sampled at a time.
The procedure has also been revised to ensure a representative >
sample is obtained from the demineralizer being borated.- +
V. Date of Tull Como11ance:
H14P is in full compliance at this time.
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The Light ,
c o m p a n y soutunn Projn: unuie Cennetleig station P. O. Bn FH Wadi.onh.Tu n 77o3
Houston LI htin & Power
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August 31,1995
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ST.HL.AE.3547
l File No.: C26 s
10CFR$0.73
U. S. Nuclear Regulatory Commission
Attention: Document Control Desk
Washington, DC 20$$$
South Texas Project Electric Cenerating Station
Unit 1 ,
Docket No. STN $0 498 -
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Licensee Event Report 90 006 Regarding
a Manual Reactor Trip Due to Full closure of a
Teedveter Isolation Valve Durine Partial Stroke Testine
Pursuant to 10CTR$0.73, Houston Lighting & Power Company (HIAP) submits
the attached Licensee Event Report (1.ER 90 006) regarding a manual reactor
trip due to full closure of a feedvater isolation valve during partial stroke
, testing. This event did not have any adverse impact on the health' and safety *
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of the public.
If you should have any questions on this matter, please contact
Mr. S. M. Head at (512) 972 7136 or myself at (512) 972 7921.
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Warren H. Kinsey,
Vice President
Noclear Generation
SMH/aap
Attachment: LER 90 006 (South Texas / Unit'1)
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South Teiss Project Electric (4nerating Station ,
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cc:
Regional Administrator, Region IV Rufus S. Scott
Nuclear Regulatory Commission Associate General Counsel ,
611 Ryan Plaza Drive Suite 1000 Houston Lighting & Power Company
Arlington, TX 76011 P. O. Box 61867
Houston, TX 77208
Coorge Dick, Project Manager
U.S. Nuclear Regulatory Commission INPO
Washington, DC 20555 Records Center
1100 circle 75 Parkway
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J. 1. Tapia Atlanta, CA 30339 3064
Senior Resident Inspector
c/o U. S. Nuclear Regulatory Dr. Joseph M. Hendrie
commission 50 Be11 port Lane
P. O. Box 910 Be11 port, NY 11713
Bay City. TX 77414
D. K. Lacker
J. R. Novman, Esquire Bureau of Radiation Control
Newcan & Holtzinger, P.C. Texas Department of Health
1615 L Street, N.W. 1100 West 49th Street
Washington, DC 20036 Austin, TX 78704
D. E. Ward /R. P. Verret
Central Power & Light Company
P. O. Box 2121
Corpus Christi, TX 78403
J. C. lanter
Director of Generation
City of Austin Electric Utility
721 Barton Springs Road
Austin, TX 78704 ,
R. J. Costello/M. T. Hardt
City Public Service Board *
P. O. Box 1771
San Antonio, TX 78296 ,
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Revised 12/15/89
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'""' Manual Reactor Trip Dae to Full Closure og a
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On July 30.1990, Unit 1 was in Mode 1 at 1004 power. At approximately 1946,
Feedwater Isolation Valve 1A fully closed during a partial stroke surveillance
test. The resultant loss of feedwater flow caused a decrease in steam
generator level and the reactor was manually tripped. The unit was stabilized
with the exception of level in Steam Cencrator 1A which did not recover. due to
a mispositioned recirculation test valve in the Train A Auxiliary Feedwater
System (AFV). The recirculation test valve us returned to the required
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position and Steam Cenerator 1A level was recovered. The Teedvater Isolation
'
Valve closure was caused by a technician inadvettently contacting the wrong
terminal with a test jumper. The cause of the miepositioned recirculation
test valve could not be conclusively established; hswever it is likely that
the valve was not correctly repositioned during a sur >eillance test prior to
the event, and this error was nct discovered due to a lack of adequate
independent verification. Corrective actions include: issuance of training
bulletins concerning use of junpers; evaluation of alternative designs to
obviate the need to perform the partial stroke test with jumpcies; and.
issuance of a memorandum to operations personnel to reenforce the requirements
pertaining to independent verification.
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DESCRIPTION OF EVENT:
on July 50,1990, Unit 1 was in Mode 1 at 1006 power. At 1946, Feedwater
Isolation Valve (WIV) 1A fully closed during performance of a partial stroke
,
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surveillance test. Steam Cenerator (SC) 1A level began decreasing and the ,
reactor was manually tripped since an automatic reactor trip was imminent due
to low steam generator water level. The turbine tripped, Feedwater Isolation
occurred on low Reactor Coolant System average temperature, and Auxiliary
Feodwater (AW) flow initiated on low. low steam generator level as expected.
,
No other Engineered Safety Feature actuations occurred during this event.
Emergency Operating Procedures were entered and the plant was stabilized with
'
the exception that level did not recover in Steam Generatcr 1A as expected.
Operations personnel determined that a recirculation valve on the 'A' train of
AW was nispositioned causing the flow to return to the Auxiliary Feedwater
Storage Tank (AWST). The recirculation valve was repositioned to recover SC
1A level. The NRC was notified of this event at 2135 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.123675e-4 months <br />.
The WIV's are hydraulically operated with a nitrogen charge in the upper
cylinder. The valve is closed by opening one or both of two solenoid valves
in parallel which dumps hydraulic fluid back to a reservoir; this allows the
nitrogen charge to drive the valve closed. The partial stroke test verifies
that both solenoids open and the WIV closes to the 906 position. Solenoid
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positio. is sensed by reed switches connected to the test circuitry. The
solenoids and reed switches are located within the valve yoke and are
difficult to maintain at power. If a reed si' itch is not functioning
cort ectly, as is the case with WIV 1A, an 'a.' ternate * partial stroke test
prot edure using jumpers is employed which allovs testing each solenoid
individually.
The 'siternate" partial stroke test procedure specit'?es use of alligator clips
to connect jumpers. Prior to the event, a technician had installed the
jumpets in a relay cabinet as specified in the test procedure. However, prior
to actaally conducting the stroke test, the alligator clip of a landed jumper
slipped off and Cell to the floor. In the process of relanding the jumper,
contact was inadvertently made with an adjacent terminal, causing WIV 1A to
close.
During the post. trip recovery process, Operations personnel observed that
Steam Generator 1A level continued to decrease even though the associated AW
flow was approximately 600 gpa. The 'A' train AW pump was secured af ter
receiving a low discharge pressure alars. Cross connect valves were opened in
an attempt to feed Steam Cenerator 1A from a different AW train; however,
this proved unsuccessful. Subsequently, the "A* train recirculating test
valve was discovered to be locked open instead of being in the required
' locked closed' position. This condition diverted AW flow back to the AWST,
thereby preventing AW flow from entering Steam Generator 1A. The
recirculation test valve was repositioned and AW flow was established to
Steam Generator 1A.
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An invest 15ation determined that the last known time the recirculation valve
was manipulated was on July 26 during a monthly AW inservice pump test.
There is no record of any other activities that would have caused the valve to ,
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be operated between July 26 and the date of the event. There is also no
evidence of maliciousness or tampering. However, it was determined that a
less than adequate independent verification was performed on the part of the !
two operators assigned to manipulate the valve during the July 26 test.
Independent verification is the act of checking a condition, such as valve
position, separately from establishing the condition or component position.
Contrary to this philosophy, it was determined that both operators were
present at the valve at the time it was to be closed, thus violating the
intent of independent verification. It has been concluded, therefore, that ,
the valve was apparently not correctly positioned by one operator (possibly '
due to the orientation of the valve), and that this condition was not
, discovered by the second operator due to a lack of adequate independent
verification.
CAUSE OF EVENT:
The direct cause of the manu31 reactor trip was a failed closed feedwater
isolation valve. The failed. closed feedwater isolation valve was caused by a
technician inadvertently contacting the wrong terminal with a test jumper. A
f contributing factor was that the test procedure specified use of alligator
clips, which are prone to fall off the tensinals used during the test.
Additional contributing factors are that the WIV's solenoid valve reed
switches were not functioning, and the design is such that they are difficult
to maintain at power. With the reed switches not functioning, a successful
partial stroke test could not be performed without the use of jumpers.
The cause of the mispositioned AW recirculation valve could not be
conclusively established; however, it is likely that the valve was not
correctly positioned by one operator'and that this error was not discovered
due to a lack of adequate independent verification on the part of a second
operator.
ANALYSIS OF EVENT:
Reactor Protection System and Engineered Safety Features actuations are
reportable pursuant to 10Cnt50.73.(a)(2)(iv). All safety systems responded as
expected, with the exception of Auxiliary Feedwater System Train A. Steam
Cenerator 1A level decreased significantly and remained low for approximately
one hour because AW flow was diverted back to the AWST due to a locked.open
recirculation test valve. A minimum wide range level of 31% was achieved at
approximately 50 minutes after the trip. An adequate heat sink was maintained
during the event by maintaining AW flow to "B", 'C', and 'D' steam
geneav ors.
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Technical Specification 3.7.1.2 requires at least four independent steam
l getierator auxiliary feedwater pumps and associated flow paths to be operable
in Modes 1, 2, and 3 including three motor. driven and one turbine driven ;
pumps. Under the worst case Design Basis Accident scenarios, including single .
i failure, one train of A W is adequate to cool the RCS even if the 'A' train of l
l AW is out of service. In recognition of this fact, the Technical >
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Specification allows an unlimited outage time for the 'A' train of AN with
the stipulation that action be immediately initiated to return the 'A' train
to service. Upon discovering the cause of the inoperability of 'A' train,
action was immediately taken to return the train to service. Since the Design
Basis Accident can be adequately mitigated with the 'A' AW train
out of service, this particular event had mi0imal safety consequences.
If the mispositioned valve had occurred on one of the other A W trains, the
worst case scenario is a main ateam line break ar a feedwater line break that
is assumed to remove the cooling capacity of the AW train on the affected
steam generator. For these events the following cases were analyzed:
Train B Valve Mispositioned: For this sconario, the worst case
situation would arise if the break were located in the 'C' train. The
AW design is such that if the single failure is assumed to be in the
'A' actuation train of the Solid State Protection System, then neither
the 'A' or 'D' trains of A W would be automatically actuated. However,
one of the early steps in performance of the F.mergency Operation
Proceduros is verification of AW actuation. AW flow would be manually
initiated by control room personnel, thus providing cooling flow to the
steam generators.
Train C Valve Mispositioned: This scenario is similar to the 'B' train
scenario described above.
Train D Valve Hispositioned: For this case, the 'D' train is, .
unavailable due to the valve being mispositioned. In addition, one
train of AW is assumed unavailable due to the break and one train of
AW is unavailable due to a single failure, i.e., a standby diesel
generator failed to start under loss of alternating current. This would
still leave one train of AW available to provide cooling to the RCS.
Since it is possible to readily provide flow to at least one steam generator
with a locked open recirculation valve on any AW train, the safety
consequences of a locked open valve on any one AW train are minimal.
The above cases have been analyzed in the Auxiliary Feedwater System
Reliability Evaluation provided in Appendix 10A of the Updated Final Safety I
Analysis Report. Specifically, this reliability study included the assumption I
t. hat a recirculation valve would be mispositioned with a frequency of 1 in 200
manipulations. STP experience is consistent with this assumption.
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l COPJtECTIVE ACTI@
The following corrective actions are being taken as a result of this event:
1) A training bulletin will be issued by September 12, 1990 to 14,C
Technicians which will discuss this event and reemphastae individual
responsibilities in regard to critical testing manipulations.
2) The partial stroke surveillance test procedures as well as other
surveillance procedures that use jumpers will be reviewed to develop
enhancements that can minimize the potential for reactor trips or
Engineered Safety Teatures actuations. This review will be
completed by December 7,1990.
3) An evaluation will be performed to determine if an alternative
design can be developed which would allow for partial stroke testing
of the IVIVs without the use of jumpers. This evaluation will be -
completed by January 31, 1991.
4) Valve lineups were performed immediately and independently verified
on various valves in the major flow paths in the following
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safety.related systems for both Unit 1 and Unit 2: Auxiliary
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Teedwater, Containment Isolation, Main peedwater, Containment Spray,
and Safety injection. Valve lineups were also performed on
accessible Engineered Safety Teature valves in the tecked Valve
Program and Standby Readiness 1.ineups were performed on the Standby
Diesel Generators on both Unit 1 and Unit 2. No deficiencies were
identified during these lineup checks.
5) The operators involved in the ATV valve manipulation were counseled
. as to the appropriate methods for performing independent
verification.
6) A memorandum has been forwarded to the operating staff reemphasizing
the need to 'self verify * all sanipulations to ensure that the
desired result has in fact occurred.
7) A memorandum has been forwarded to the operating staff reemphasizing
the importance of and requirements for independent verification and
the proper methods of verifying valve positions.
8) This event will be included in operator continuing training, with
emphasis placed on the ramifications of misaligning the Auxiliary
Teedwater System and the requirements for Independent Verification.
This action will be completed by November 30, 1990,
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ADDITIONAL INftRMATION:
There has been a previously reported event (IDt 2 89 019) concerning a reactor i
- trip caused by a WIV failing closed; however, the event was not associated ,
with a test jumper but was caused by a failure in the test circuitry. .
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