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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
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c- 9 MAR - 81988 In Reply Refer To:
Dockets: 50-498/0L-88-01 Houston Lighting & Power Company ATTN: J. H. Goldberg, Group Vice President, Nuclear P.O. Box 1700 Houston, Texas 77001 Gentlemen:
SUBJECT:
OPERATOR LICENSING EXAMINATIONS AT SOUTH TEXAS PROJECT FACILITY In a telephone conversation between Messrs. Glen Weldon, Manager, Operator Training and John L. Pellet, Chief Operator Licensing Section, arrangements were made for the administration of reactor operator and senior reactor license examinations at the STP facility during the weeks of May 16 and 23, 1988.
In order for NRC to meet the above schedule, it will be necessary for facility management to furnish the approved reference material listed in Enclosure 1, "Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations," to the extent it is available at your facility, by March 25, 1988. Any delay in receiving properly bound and indexed reference material may result in a delay.in administering the examinations. Examinations are scheduled far in advance with considerable planning to utilize limited examiner manpower and to meet the examination dates requested by the various facility licensees. Therefore, missing the March 25, 1988 deadline, even by a few days, may result in a long delay because it may not be possible to reschedule examinations for other facility licensees. Mr. Weldon has been advised of our reference material requirements.
The facility management is responsible for providing adequate space and acconnodations in order to properly conduct the written examinations.
Enclosure 2. "Administration of Reactor / Senior Reactor Operator Licensing Written Examinations," describes NRC requirements for conducting these examinations. Mr. Weldon has also been informed of these requirements.
Enclosure 2 also contains the Rules and Guidance that will be in effect during the administration of the written examination. The facility management is responsible for ensuring that all candidates are aware of these rules.
JJ Y i OE C:0LSh D:DRS D:DRPD Recon r LMcCrory:cs JLPellet JLMilhoan LJCallan JLPellet
/ 7 /88 3/1/88 3/7/88 3/}/88 3/7/88 8803140055 880308 PDR
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ADOCK 05000498 V DCD
Houston Lighting & Power .
Company The facility staff review of the written examination will be conducted in- i accordance with the specifications in Enclosure.3, "Requirements for Facility Review of Written Examination." Mr. Weldon has been informed of these requirements.
Reactor operator and senior reactor operator license applications for all candidates should be submitted at least 60 days before'the first scheduled examination date so that the NRC will be able to review the training and experience of the candidates, process medical certifications, and issue examiner assignments. If copies of the applications are not received at least 30 days before the examination date, it is likely that a postponement will be necessary. All training and qualification requirements must be met by each candidate prior to application submittal.
Until December 31, 1988, in order to allow you to modify your training program I so that all training is completed prior to submission of an application, you
. are permitted to request an exemption of this certification requirement. This can be done by lining through the language in Item 19.b on the application, NRC Form 398, concerning completion of licensee requirements and by referencing a separate attachment to the application containing the following language:
The applicant has not yet successfully completed the licensee requirements to be licensed as an Operator / Senior Operator. However, he/she will have completed them prior to the examination. Upon completion of the requirements, a certification to that effect will be i provided as a further addendum to this application. in the interim, it li is from requested, this requirement, pursuant as to 10 CFRin55.11, contained 10 CFRthat the app 55.31 (a) cant be exempted (4). :
t i '
Printed Name and Signature-Training Printed Name and Signature-Senior Coordinator Management Representative on Site t Once the applicant completes the training requirements, an addendum to NRC Form 398 would be required to be sent. This addendum must be received prior to the cxamination date. The format and content of this addendum should read '
as follows-i I l
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' Houston Lighting & Power Company.
Addendum to NRC Form 398 Application of Facility Name Printed Name and Signature-Training Printed Name and Signature-Senior Coordinator Management Representative on Site This is to certify that has successfully completed the licensee requirement for licensing, as required under 10 CFR 55.31(a)(4).
This request for infomation was approved by the Office of Management and Budget under Clearance No. 3150-0101, which expires May 31, 1989. Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management Room 3208, New Executive Office Building, Washington, DC 20503.
Thank you for your consideration in this matter. If you have any questions regarding the examination procedures and requirements, please contact Messrs. Stephen L. McCrory, Chief Examiner, at (817)860-8265 or John L. Pellet, Chief Operator Licensing Section, at (817)860-8159.
Sincerely, Original Signed By L 1. Callan L. J. Callan, Director Division of Reactor Projects
Enclosures:
- 1. Reference Material Requirements
- 2. Written Exam Administration Requirements
- 3. Facility Review Requirements cc w/ enclosures:
Houston Lighting & Power Company ATTN: M. A. McBurnett, Manager Operations Support Lic.
P.O. Box 289 Houston, Texas 77483 (cc cont'd. next page)
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i
-Houston Lighting & Power; -
4- !
Company Houston Lighting & ~ Power ' Company ATTN: Gerald E. Vaughn, Vice President Nuclear Operations P.O. Box 1700
~ Houston, Texas 77001 Houston Lighting & Power Company i ATTN: S. L. Rosen i P.O. Box 289' l Houston, Texas 77483 Central Power & Light Company ATTN: R. L. Range /R. P. Verret j!
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 Elec. Utility ATTN: R. J. Miner, Chief Operating 4 Officer '
721 Barton Springs Road Austin, Texas 78704 l
Texas Radiation Control Program Director I bec to DMB (IE42) bec distrib. by RIV:
DRP RRI-0PS R. D. Martin, RA RRI-CONST.
SectionChief(DRP/D) RPSB-DRSS ,
RIV File MIS System Lisa Shea, RM/ALF RSTS Operator R. Bachmann, OGC H. Bundy j P. Kadambi, NRR Project Manager R. Taylor TSS R. Hall i DRS S. McCrory i J. Pellet )
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ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSitlG EXAMINATIONS
- 1. Existing learning objectives and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thennodynamics, etc.).
Training materials should iaclude al' substantive written materiai used for preparing candidates for initial R0 and SR0 licensing. The weitten material should be inclusive of learning objectives and the details presented during lecture, rather than outlines. Training materials should be identified by plant and unit, bound, and indexed. Failure to provide complete, properly bound and indexed reference material will rerilt in canceling and rescheduling of the examinations. Training materials which include the following should be provided:
o System descriptions including descriptions of all operationally relevant flow paths, components, controls, and instrumentation.
System training material should draw parallels to the actual procedures used for operating the applicable system, o Complete and operationally useful descriptions of all safety-system interactions, and, where available, B0P system interactions under emergency ard abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
o Training material used to clarify and strengthen understanding of emergency operating procedures, o Comprehensive theory material that includes fundamentals in the area of theory of reactor operation, thermodynamics, heat transfer and fluid flow, as well as specific applications to actual in-plant components. For example, mechanical theory material should include pump theory as well as descriptions of how these principles actually apply to major plant pumps and the system in which they are installed (i.e., reactor coolant pumps, all ECCS pumps, recirculation pumps, feedwater and emergency feedwater pumps). Reactor theory material should include descriptions that draw explicit ties between the fundamental and actual operating limits followed in the plant (e.g.,
reacter theory material should contain explanations how principles relate to the actual curves use by operators to verify shutdown margin or calculate an ECP).
- 2. Procedure Index (alphabetical by subject).
- 3. All administrative procedures (as applicable to reactor operation or safety).
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- 4. All integrated plant procedures (nonnal or general operating procedures).
- 5. Emergency procedures (emergency instructions, abnormal or special procedures). l 1
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- 6. Standing orders (important orders that are safety-related and may supersede the regular procedures).
- 7. Fuel handling and core-loading procedures, (initial core-loading procedure, whenappropriate). ,
- 8. Radiation protection manual (radiation protection manual or procedures).
- 9. Emergency plan implementing procedures,
- 10. Technical Specifications.
- 11. System operating procedures.
- 12. Piping and instrumentation diagrams, electrical single-line diagrams, or i flow diagrams.
- 13. Technical data book, and/or plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the facility.
- 14. Questions and answers that the facility licensee has prepared (voluntary by facility licensee).
- 15. The following on the plant reference simulation facility:
- a. List of all readily available initialization points.
- b. List of all preset malfunctions with a clear identification number, i The list should include cause and effect information. Specifically.
. for each malfunction a concise description of the expected result, or range of results, that will occur on implementation should be provided. Additionally', an indication of which annunciators are to be initially expected should be given.
- c. A description of simulator failure capabilities for valves, breakers, indicators, and alarms,
- d. Where the capability exists, an explanation of the ability to vary the severity of a particular malfunction should be provided, i.e.,
the ability to vary the size of a given LOCA or steam leak, or the ability to cause a slow failure of a component such as a feed pump, turbine generator, or major valve (e.g., drifting shut of a main feedwatercontrolvalve).
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} e. An indication of modeling conditions or problems that may impact the-examination. '
- f. Identification of unknown Perfonnance Test Failures not yet completed,
- g. Identification of significant differences between the simulator and the control room,
- h. Copies of facility licensee generated scenarios that ex candidates to situations of degraded pressure control (pose PWR), the degraded heat removal capability (PWR and BWR), and containment challenges (BWR) may be provided (voluntary by facility licensee).
- 1. Simulator instructors manual (voluntary by facility licensee).
J. Description of the scenarios used for the training class (voluntary by facility licensee). I
- 16. Additional material required by the examiners to develop examinations that meet the requirements of these standards and regulation?,
The above reference material should be approved, final isates, and so marked.
If a plant has not finalized some of the material, the chief examiner is responsible for ensuring that the most complete, up-to-date material is
- available and that agreeoent has been reached with the facility licensee for limiting changes before the administration of the examination. All procedures ,
and reference material should be bound or IN THE FORM USED BY THE CONTROL ROOM .
OPERATORS, WITH appropriate INDEXES or TABLES OF CONTENTS so that they can be used efficiently.
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ENCLOSURE 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS ;
- 1. A single room shall be provided for completing the written examination.
.The location of this room and supporting rest room facilities shall be such as to prevent contact with all other facility licensee and/or contractor personnel during the duration of the written examination. If necessary, the facility licensee should make arrangements for use of a suitable room at a local school, motel, or other building. Obtaining this room is the responsibility of the facility licensee.
- 2. Minimum spacing is required to ensure examination integrity as determined by the chief examiner. Minimum spacing should be one candidate per table, with a 3-foot space between tables. No wall charts, models, and/or other training materials shall be present in the examination room. ;
- 3. Suitable arrangements shall be made by the facility licensee if the candidates are to have lunch, coffee, or other refreshments. These arrangements shall comply with Iter 1 above. These arrangements shall be '
reviewed by the chief examiner and,or proctor.
- 4. The facility licensee shall provide pads of 8 1/2- by 11-in. lined paper t in unopened packages for each candidate's use in completing the examination. ;
The examiner shall distribute these pads to the candidates. The facility ;
licensee shall provide unmarked steam tables for candidate use as requested [
by the chief examiner. When requested by the chief examiner the facility ,
licensee shall also prepare copies of large documents (i.e. Technical L Specification'. . Emergency Plan Implementing Procedures. Emergency Operating Procedures, etc.) for use by the candidates. Such requests will normally be made known to the facility licensee the working day prior to the written examination. .11 ' other reference material needed to complete the examination shall be furnished by the examiner. Candidates may bring pens, pencils, nonpro;ramable calculators, or slide rules into the examination room. No other equipment or reference material shall be allowed. .
- 5. Only black ink or dat k pencils should be used for writing answers to questions.
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ENCLOSURE 3 !
REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATIONS
- 1. There shall be no review of the written examination by the facility {'
licensee staff before or during the administration of the examination. '
Following the administration of the written examination, the facility licensee staff-shall be-provided a marked-up copy of the examination and the answer key, !
- 2. The facilit/ licensee will have five (5) working days from the day the !
written examination is given to submit formal comments. The formal comments will be approved by the highest level of corporate management for plant operations, e.g., Vice President for Nuclear Operations, and submitted to the Region IV office with a copy to the Section Chief for Operator Licensing. Comments not submitted within five (5) working days will be incorporated into the grading process on a case by case basis as .
determined by the Section Chief. No grading will be done until the l formal commer,ts are received and resolved. If the formal comments are i not received by the deadline, the final examination results may be i delayed several weeks since the grading may have to be rescheduled in a :'
later time slot.
- 3. The following information shall be provided for each individual comment: i
- a. NRC question number I I
- b. Facility licensee comment
- c. Copy of supporting documentation (the reference may be cited if the !
document is held by the Operator Licensing Section) i NOTES: 1. No change to the examination will be made without i submittal of, or proper reference to, complete, current, and ;
approved reference material. ;
- 2. Comments made without a clear, concise, facility licensee i recommendation, will not be addressed.
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