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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 ML20056A7961990-08-0303 August 1990 Advises That Util Response to Generic Ltr 88-06 Re Implementation of Spds,Acceptable 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 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 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 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 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 ML20247H5281989-09-12012 September 1989 Forwards Insp Repts 50-498/89-36 & 50-499/89-36 on 890821-25 & Notice of Violation 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 ML20245K3541989-08-10010 August 1989 Forwards Insp Repts 50-498/89-23 & 50-499/89-23 on 890701-31.No Violations Noted.Actions Taken Re Previous Insp Findings Also Examined IR 05000498/19890161989-08-0909 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/89-16 & 50-499/89-16.Implementation of Corrective Actions Will Be Reviewed During Future Insp 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 05000498/1988001
Text
. _ -_ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - - _ _ __ . - _ _ _
MAR 2 41988 l
4
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In Reply Refer To:
~
,
Dockets: 50-498/88-01 1
50-499/88-01
!
Houston Lighting & Power Company
ATTN: J. H. Goldberg, Group Vice
President, Nuclear
P.O. Box 1700
Houston, Texas 77001
Gentlemen:
Thank you for your letter of March 1,1988, in response to our letter and l
,
Notice of Violation dated February 10, 1988. We have reviewed your reply and
find it responsive to the concerns raised in our Notice of Violation. We will
review the implementation of your corrective actions during a future inspection 8
{
to determine that full compliance has been achieved and will be maintained.
Sincerely,
t
'
Original Signed By
A. B. Beach
1
h J. Callan, Director
j. Division of Reactor Projects i
cc: .
Houston Lighting & Power Company l
ATTN: M. A. McBurnett, Manager !
Operations Support Licensing
P.O. Box 289
Wadsworth, Texas 77483
. ,
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RIYJD ' RS lDR C SD j D:]RP l
JJaudon/cjg hoan on e51e LJcallan
7j /p/88 # LMi}/88
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. _ _ _ _ _ _ _ _ __ _ _ _ _ - _ .__ _ . _ _ _ _ _ _ _ _ _ _ _ ___
4
Houston Lighting & Power Company -2-
a
cc: (cont'd)
Houston Lighting & Power Company
ATTN: Gerald E. Vaughn, Vice President
Nuclear Operations
P.O. Box 1700
Houston, Texas 77001
Houston Lighting & Power Company
ATTN: S. L. Rosen
P.O. Box 289
Wadsworth, Texas 77483
Central Power & Light Company
ATTN: R. L. Range /R. P. Verret
P.O. Box 2121
Corpus Christi, Texas 78403
City Public Service Board
ATTN: R. J. Costello/M. T. Hardt
P.O. Box 1771
San Antonio, Texas 78296
City of Austin Electric Utility
ATTN: R. J. Miner, Chief Operating
Officer
721 Barton Springs Road
Austin, Texas 78704
Texas Radiation Control Program Director
bec:
bec to DMB (IE01)
bec distrib. by RIV:
DRP RRI-0PS
R. D. Martin, RA DRS
SectionChief(DRP/D) RPSB-DRSS
MIS System RIV File
Lisa Shea, RM/ALF RSTS Operator
R. Bachmann 0GC D. Hunnicutt
P. Kadambi, NRR Project Manager TSS
D. Powers
!
.- . , _ , , _ - , . , . . ,- - _ . - - -
- _ _ _ _
'
The Light
' '
company PO. Bos 1700 Houston, Texas 77001 (713) 228 9211
ilouston Lighting & Power
, March 1, 1988
ST-HL-AE-2541
File No.: G2.04
t' - ' i l
U. S. Nuclear Regulatory Comission
Attention: Document Control Desk
Washington, DC 20555
South Texas Project Electric Generating Station
Unit 1
.
Docket No. STN 50-498
Response to Violatiens 8801-01 through 8801-08
HL&P has reviewed the Notices of Violation included in inapection Report
88-01 and submits the attached responses pursuant to 10CFR Part 2.
If you have any questions, please contact Mr. M. A. McBurnett at
(512)972-8530.
Wy
G. E. Vaughn
Vice President
Nuclear Plant Operations
GEV/WH/kr.
Attachment: Responses to Notices of Violation
.
j-
MAR 2 2
,
A Subsidiary of Houston Industries' incorporated
'
NL.88.053.03
['Y Y -g[O-3OK g @f g
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CT-HL-AE-2541
File No.: G2.04
Page 2
CCI
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Regional Administr,ator 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 1700
Houston. TX 77001
N. Prasad Kadambi. Project Nanager
U. S. Nuclear Regulatory Commission INPO
1 White Flint North Records Center
'
11555 Rockville Pike 1100 Circle 75 7'Tkway
Rockville. MD 20859 Atlanta. Ga. 30339-3064
Dan R. Carpenter
Senior Resident Inspector / Operations
c/o*U. S. Nuclear Regulatory
Commission
j P. O. Box 910
Bay City. TX 77414
J. R. Newman. Esquire
Newman & Holtzinger. P.C.
1615 L Street. N.W.
Washington, DC 20036
R. L. Range /R. P. Verret
Central Power & Light Company
P. O. Box 2121
Corpus Christi. TX 76403
R. John Miner (2 copies)
Chief Operating Officer
City of Austin Electric Utility
721 Barton Springs Road
l
'
Austin. TX 78704
R. J. Costello/M. T. Hardt
City Public Service Board
P. O. Box 1771
San Antonio, TX 78296
.
.
Revised 02/03/88
NL.LER. DISTR.1
.
. . Attachment
ST-HL-AE-2541
Page 1
.
A. Statement of Violation 8801-01:
Hich Head Safety Iniection Pump Controls System Lineup
Technical Specification 6.8.1 requires that written procedures be
established, implemented, and maintained covering the activities
recommended in Appendix A of Regulatory Guide 1.33. Revision 2. February
1978. Section 3 of this appendix recommends procedures for operation of
I the emergency core cooling system.
Procedure IPOP02-SI-0002. Revision 6 dated December 30. 1987 Safety
Injection System Initial Lineup. has been established in accordance with
Technical Specification 6.8.1 to implement. inter alia. Technical
,
l
Specification 3.5.3.
Contrary to the above, on January 7. 1988, the NRC inspector found that (
this procedure was not adequate to control the alignment of the high head
saf ety injection pumps in Mode 4. Forms 3. 7. and 11. providing the
i Mode 4 alignment of saf ety injection system Trains A. B. and C.
respectively, specified the required position for the high head saf ety
injection pump main control board handswitches to be "PTL" (Pull to
Lock). Following this procedure would have made all three high head
i
saf ety injection pumps inoperable in Mode 4. contrary to Tectoical ,
Specification 3.5.3.
6
,
Reason for violation
The root cause of this violation was inadequate review of the procedure ;
to assure its consistency with the requirements of the applicable
'
Technical Specifications.
' Corrective actions that have been taken: ,
1
1. Procedure IPOP02-SI-0002 has been revised to correct Forms 3, 7. and
11 to indicate the proper handswitch alignments for all modes.
2. A review of other system lineup procedures was performed to ensure
i their consistency with the Technical Specifications.
3. Procedure OPGP03-ZA-0002 has been revised to incorporate requirements 7
for an independent technical review of new procedures. l
Corrective actions that will be taken: 5
r
No f urther action is required.
.
Full Compliance l
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l The plant is in full compliance.
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NL.88.053.03
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ST-HL-AE-3541
Page 2
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B. Statement of Violation 8801-02: ,
Temporary Modifi ca ti ons i
Technical Specification 6.8.1 requires that written procedures be
established, implemented, and maintained covering the activities
recommended in Appendix A of Regulatory Guide 1.33. Revision 2.
February 1978.
Procedure OPGP03-ZO-0003. Revision 7. dated September 12. 1987
"Temporary Modifications and Alterations." has been established in
accordance with this Technical Specification.
,
8
Section 4.7 of this procedure requires that the control room hard copy of
piping and instrumentation drawings affected by a temporary modification
I be annotated and clouded in red to identify the existence of a temporary
modification. It further requires that a copy of the temporary
modification request be attached to the drawing and a notation of which
' drawings were updated to be made on the original of the temporary
modification request.
i
Contrary to the above, on January 5, 1988. the NRC inspector found that !
l the requirements of Section 4.7 of Procedure OPGP03-ZO-0003 had not been l
. met f or Temporary Modification TI-EV-87-252 f or Drawing 5R289F05038 in
that no markup had been made.
i
<
j Reason for violationt
'
The root cause of this violation was the Systems Engineer's lack of
attention to detail in following the procedure. A contributing factor
was a lack of positive controls (e.g., signature verifications) on the 1
Temporary Modification Request (THR) form to ensure compliance with the
l
procedure. Another contributing factor was a lack of clarity in the . '
-
j
procedure with regard to the treatment of blank and blind flanges. [
' ;
i Corrective actions that have been takent
i
1. Drawing 5R289F05038 was updated in compliance with procedure
OPGP03-ZO-0003 (i.e., red lining of drawing, attaching a copy of the
TMR. noting drawing update)
2. A review of outstanding temporary modifications was performed against l
'
the requirenehts of the procedure. Identified discrepancies were
corrected. t
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NL.88.053.03
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Attechnent
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C ST-HL-AE-2541 ;
- Page 3
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3. Procedure OPGP03-ZO-0003. Temporary Modifications and Alterations, j
was revised to clarify treatment of blank and blind flanges. The j
l
< procedure was also revised to implement the following additional
controls:
a. Identification of Key Drawings on the' Temporary Modification f
Request.
$ b. Addition of a confirmation signature indicating that the affected i
drawing (s) have been red lined. ;
j c. Addition of a restoration signature indicating that the drawings
i
have been restored to normal after temporary modification is '
removed.
<
4. System Engineers have been formally advised of the procedural changes j
,
and the requirement to follow them in detail.
Corrective action that will be taken $
I
i No further action is required. ;
Full Compliance
I
The plant is in full compliance. l
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ST-HL-AE-2541
Page 4
C. Statement of Violatior 8801-03:
Locked Valves
- Technical Specification 6.8.1 requires that written procedures be
established, implemented, and maintained covering the activities
recommended in Appendix A of gegulatory Guide 1.33. Revision 2.
February 1978. Section 3 of this appendix recommends procedures for
operation of the emergency core cooling system.
Procedure 1 POP 02-SI-0002. Revision 6. dated December 30, 1987 "Safety
Injection System Initial Lineup." has been established in accordance with
this Technical Specification.
Form 9 of this procedure. Initial Lineup Train C. requires Manual Valves
SI-0059C. SI-0224C. ar.d SI-0070C to be locked closed.
Contrary to the above on January 6. 1988, the NRC inspectors found that
SI-0059C was closed, but not locted and that SI-0224C and SI-0070C were
closed but inadequately locked. The cables and padlocks on these latter
two valves could easily be removed by hand.
Reason for violation:
The root cause of the violation was lack of attention to detail on the
part of operations personnel who inspect valves in accordance with the
Locked Valve Program in that inadequately locked and/or unlocked valves
were not identified and corrected in accordance with the Locked Valve
Program OPGP03-20-0027.
Corrective actions that have been taken:
1. Valves SI-0070C and SI-0224C were locked and valve SI-0059C was
tagged as allowed by procedure.
2. valves required to be locked in accordance with the Locked Valve
Program were inspected for proper position and locking devices or
administrative controls. None were found to be improperly
positioned. Those that were found to be inadequately locked were
either properly locked or administrative controls were implemented
through the station clearance process.
Corrective actions which will be taken
No further action is required.
Full Compliance
.
The plant is in full compliance.
.
NL.88.053.03
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' i
' * AttCchment
ST-HL-AE-2541
Page 5
D. Statement of Violation 8801-04:
Containment Intecrity
,
Technical Specification 3.6.1.1 requires that containment integrity be .
maintained in Modes 1. 2. 3. and 4. The conditions of license
regulation. 10CTR50.54 invokes Appendix J to 10 CTR 50 to define
containment integrity and to limit combined leakage measured by test, to
less than 0.6 La.
Contrary to the above the licensee was in Mode 4 on October 31 and
Fovember 1. 1987. With Containment Isolation Valve BIRAMOV0003. not
tested for local leak rate after maintenance so that the ability to moet
the 0.6 La criterion was not determined.
Reason for violation:
The root causes of the event were determined to be:
1. Failure to provide maintenance planners and maintenance supervisors
with adequate training concerning post maintenance testing (PMT)
requirements regarding containment integrity.
2. Failure to identify the appropriate PMT requirements f or local leak
rate testing on the MVR during supervisory review.
Corrective actions that have been taken:
1. A Local Leak Rate Test was satisf actorily performed on the subject
valve and it was returned to an operable status at approximately 2200
hours on January 6. 1988.
2. A review c,' MVRs and LLRT records was conducted to ensure that proper
testing had been done to assure containment integrity.
3. Informatica regarding this event was discussed with maintenance
supervisory personnel and maintenance planners. The intent of these
briefinjs was to make these personnel aware of the importance of
maintaining containment integrity. Maintenance planners were advised
to discuss PMT requirements with the cognizant system engineer prior
to issuang a MWR. especially in regards to containment isolation
valves.
4. To enhance the current MVR program. NWR procedure. OPGP03-ZM-0003.
was revised to assure that the required PMTs are identified on MVRs
involving containment isolation valves.
.
9
NL.88.053.03
.
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. .
Attachment ,
ST-HL-AE-2541
.
Page 6
Corrective action that will be takent
' Training of shift supervisors and support personnel will be conducted to '
reinforce the importance of post-maintenance testing with regard to -
containment integrity requirements.
- -
Full Compliance ,
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The plant will be in full compliance upon completion of the training.
This is expected to be done by March 3 1988. ,
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ST-HL-AE-2541
Page 7
E. Statement of Violation 8801-05:
Surveillance Procedure Discrepancies
Criterion V of 10 CTR 50. Appendix B. requires, in part, that activities
'
'affecting quality be performed in accordance with approved drawings,
insttuctions, and procedures appropriate to the activity.
The licensee's approved Operations Quality Assurance Plan. Section 112.
"Test Control." Paragraph 6.4 requires that test procedure shall provide
instructions for performing tests and provisions for documenting results.
Contrary to the above, the licensee failed to follow procedures
associated with the Surveillance Program and/or failed tp provide
adequate procedure to control the activities affecting the quality of
Technical Specification surveillance as identified in the six examples
cited below: ,
.
1. In December 1987 the licensee collected 250 milliliter waste liquid i
"
discharge samples in lieu of the one liter samples required by
Procedure 1 PSP 07-WL-0001.
2. On January 7. 1988, it was f ound that Procedure OPSP07-CR-0002 was (
inadequate in that it failed to provide the necessary requirement to
calculate an average sample. Chemistry Technicians were observed to
be calculating the average sample in accordance with verbal
instructions in lieu of following the procedure.
3. On January 6. 1988, it was found the Procedures 1 PSP 02-RC-0454. 0461.
and 0462 had been improperly modified by Field Change Request to
waive Stegs 7.4.2 and 7.7.16 when reactor coolant temperature is
below 538 F in that the data sheet was not modified to support the
change. ;
4. On January 7, 1988, it was found that Procedure OPSPO4-XC-0001
Revision 1. had been improperly revised such that changes were
incorporated into an unapproved draf t of Revision 0 in lieu of an
approved copy of Revision O. resulting in a Revision 1 that contained
j draft errors. This is contrary to the requirements of
OPGP03-ZA-0002. Revision 10. "Plant Procedures."
5. On January 6 1988, it was found that Procedure 1 PSP 11-RH-0004
Revision 1. failed to contain numeric values of the acceptance
criteria due to a series _of inappropriate char.ges. This is contrary
to the requirements of OPGP03-ZE-0005. Revision 6. "Plant
Surveillance Procedure Preparation." Section 3.2.6.
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l 6. On January 6 1988, it was found that two completed surveillance test
packages for OPSPO4-DG-0001 were presented to the Plant Operations
Review Committee (PORC) for acceptance of the results based on ,
previously accomplished preoperational test information with missing ,
data. 7he packages were approved by the PORC with missing data.
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Reason for violationt !
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Item I was attributable to poor judgement by technicians who decided to
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substitute a different size container for the size specified in the
procedure.
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Item 2 was attributable to inadequate description rf required
calculations in the procedure.
Items 3. 4. and $ were attributable to a f ailure to follow procedures
regarding the use of FCRs.
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Item 6 is attributable to two factorst
1. Personnel reviewing the pre-operational test package prior to its
presentation to PORC failed to detect a copying error.
2. The level of review performed by PORC vas not of sufficient detail
and depth to detect the copying error.
Corrective actions that have been takent
Item 1: Chemical Analysis personnel have been reinstructed regarding
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the importance of f ollowing procedures verbatim.
Item 2: Chemical Analysis surveillance procedures requiring
calculations have been reviewed and revised as necessary to
ensure that adequate instruction on performance of the
calculations is provided.
Items 3-5 A Departmental bulletin was issued providing additional
guidance to NPOD personnel regarding the control of Field
Change Request changes to surveillance procedures.
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Procedure OPGPO3-ZA-OOO2 "Plant _ Procedures" was revised to
include specific guidelines for the review and implementation
of Field Change Requests.
Item 6: The data missing from the subject packages was reviewed and
approved by PORC and inserted in the file packages,
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An ISEG special investigation was conducted to review the PORC
process to recommend possible enhancemente. The
recommendations, which wele issued February 22. 1988 include
more formal control of the PORC meetings, more control of
"walk-on" items, better definition of s: ope of review.
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Corrective action that will be takent ;
Management will review the ISEG recommendations and identify any [
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improvements and a schedule for implementation by March 31, 1988.
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Full Compliance l
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The plant is in full compliance, however, enhancements to the PORC
process may be made following review and analysis of the ISEG report.
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F. Statement of Violation 8801-06:
Implementation of Technical Specification Eeauirements
Technical Specification 6.8.1 requires that written procedures shall be . 1
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established, implemented, and maintained covering activities recommended ;
in Appendix A of Regulatory Guide 1.33. Revision 2. February 1978.
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Contrary to the above, it was found on January 7.1988, that the licensee
had failed to provide test procedures, which completely implemerted the
final technical specifications as cited below:
1. Procedure 1 PSP 10-RC-0001. Revision 0, contained an acceptance
criterion calling for a figure in the technical specifications which
had been deleted when the final technical specifications were issued.
thus resulting in an incomplete and inadequate procedure for
conducting the surveillance. l
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2. Procedure OPSP10-II-0003 was found to contain an incorrect and
nonconservative equation for adjusting the core radial peaking factor [
limit f or f ractional power levels, thus resulting in an incorrect and
inadequate procedure conducting the surveillance. !
Reason for violations f
The root cause of this violation was that the process to incorporate
changes in the T9chnical Specifications into procedures did not track I
required actions to completion. t
Corrective actions that have been takent .
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1. OPSP10-II-0003 has been corrected to be consistent with the .4chnical ;
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Specifications. Procedure 1 PEPO 4-ZG-0007 has been identified as the '
proper procedure for use in RCS flow measurement in lieu of
IPSP10-RC-0001. I
2. Suf ficient review of surveillance procedures has been completed to
assure compliance with Technical Spec 2fication requirements for
operation through Mode 2.
3. Procedure OPGP03-ZA-0002 has been revised to require an independent
techn* cal review of new procedures. Requirements have beeb added to
the procedure to perform a "walk through" of new surveillence
procedures to confirm the Frecedure can be accomplished as written.
Additional procedure review criteria have been imposed by means of an
uttribute check sheet which includes items for confirming Technical
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Specification requirements.
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4. Interdepartmental procedure 3.20Q is now in ef f ect which requires
Technical Specification changes to be tracked f rom request through
implementation. It also requires a QA verification of implementation.
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Corrective action that will be taken ,
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Suf ficient review of surveillance procedures to assure that Mode 1 !
Technical Specification rrquirements are incorporated will be completed [
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prior to exceeding % power. .
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I rull Compliance l
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The plant is in compliance f or operation through Mode 2. Confirmation of
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full compliance will be achieved upon completion of the remaining reviews j
as described above. 7
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G. Statement of Violation 8801-07:
Overdue Station Problem Report Investigation
Criterion V of Appendix B to 10 CPR Part 50 and the licensee's approved ;
,
quality assurance plan require that activities affecting quality be
conducted in accordance with approved procedures. Interdepartmental
Procedure IP 1.45Q. "Station Problem Reporting." requires that corrective
investigations be completed within 17 days.
,
l Contrary to the above, on January 4 1988. 68 of 204 station problem
i reports were overdue (past 17 days) for completion.
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1- Reason for the violationt
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The root cause of the violation was inadequate assignment of resources to
prioritize and resolve the SPRs.
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Corrective actions that have been taken I
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1. The safety significance of each SPR is evaluated when the SPR is
I first initiated, and immediate action is taken if required to assure
plant safety. A review was performed which confirmed that the
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conditions described in the open SPRs have been adequately addressed
' so that plant saf ety is not adversely af fected.
2. Revision 1 of Procedure 1.450 was implemented on February 22, 1988. !
This new procedure increased management's involvement in the process
by requiring an early establishment of priority and due date by the
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Plant Manager. The revision also requires the SPR originator to take
the SPR directly to the Shif t Supervisor.
3. . Additional licensing engineers have been assigned to coordinate
resolution of SPRs. These personnel have participated in a concerted
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effort to resolve overdue SPRs. The backlog of overdue SPRs has been
reduced to an acceptable level.
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Correction action that will be tatent
No further action is required.
Full Compliance:
The plant is in full compliance.
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H. Inadecuate corrective Action (8801-08):
' Criterion XVI of Appendix B to 10 CFR Part 50 and the licensee's approved
quality assurance plan require conditions adverse to quality be proeptly I
identified and corrected. In August 1987, a quality assurance audit
[
deficiency' report was issued wh4ch identified 55 of 179 station problem
reports were overdue for completion. The deficiency was closed on the
basis that tracking responsibility for station problem report ,
investigation tracking was procedurally changed.
Contrary to the above, it was found on January 4, 1986, that the
corrective action was not adequate in that 68 of 204 station problem
,
reports were overdue for completion.
Reason for the violation:
As noted in the statement of the violation, the backlog of overdue SPRs
was identified in an audit in August 1987, and as corrective action
procedures were changed to assign responsibility for coordination of SPRs
to Licensing. Nuclear Assurance accepted this response and a follow up
audit to determine the effectiveness of the corrective action was
scheduled for February 1988. Prior to the follow-up audit, management
failed to identify that the corrective action had not been effective.
Corrective actions which have been taken:
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In accordance with the schedule adopted upon acceptance of the response
to the August 1987 audit, in February 1988 Nuclear Assurance completed
its follow-up audit of the effectiveness of the ccrrective actions. The
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follow-up audit identified inadequate effectivenesr, of the earlier
corrective action as a significant deficiency (DR S87-064. Rev.1).
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Response to DR 587-064. Rev. 1 is due by March 18. 1988. The response to
! DR S87-064. Rev. I will be reviewed by Nuclear Assurance.
The corrective actions described in response to Notice of Violation
88 01-07 have been implemented. and are expected to resolve DR S87-064.
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Rev. 1. As an interim measure, until management gains added confidence
in the effectiveness of the revisions to the SPR program. Licensing is
providing management with weekly reports of SPR status.
Corrective actions that will be taken:
As a result of the DR. a review of Station Problem Reports is being
conducted to assure that root causes were adequately addressed and that
supporting documentation properly dispositions the required actions.
This activity is expected to be complete by 60 days after the issuance of i
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the Full Power operating License.
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Full Compliance:
The plant will be confirmed to be f ull compliance utan completion of the
SPR review described above. ,
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NL.88.053.03
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