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Category:CORRESPONDENCE-LETTERS
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span ML20217M5711999-10-20020 October 1999 Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20212L2891999-10-0101 October 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 ML20212F7481999-09-24024 September 1999 Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4 ML20212F1041999-09-23023 September 1999 Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2 ML20212E6661999-09-21021 September 1999 Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure ML20212D9111999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl ML20212A7601999-09-14014 September 1999 Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211P3761999-09-0707 September 1999 Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211J3801999-08-27027 August 1999 Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20211B2861999-08-18018 August 1999 Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise ML20211C4661999-08-18018 August 1999 Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS 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 ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210R2221999-08-12012 August 1999 Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request 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 ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210D8231999-07-23023 July 1999 Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20210C3331999-07-16016 July 1999 Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 1999-09-07
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G5471990-11-26026 November 1990 Forwards Summary of NRC Understanding of Current Status of Unimplemented GSIs at Facility ML20058H5501990-11-14014 November 1990 Forwards Insp Repts 50-445/90-40 & 50-446/90-40 on 900918- 1030.Violations Noted But Not Cited IR 05000445/19900371990-11-0808 November 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-445/90-37 & 50-446/90-37 ML20058G1521990-11-0505 November 1990 Discusses Util 900529 Response to 900402 Notice of Violation.Violations 445/8923-V-01 & 446/8923-V-01 Closed, Per Insp Repts 50-445/89-23 & 50-446/89-23 ML20058G4791990-10-31031 October 1990 Forwards Summary of 901022 Meeting W/Util in Arlington,Tx Re Secondary Plant Reliability Problems at Unit 1 ML20058E6931990-10-29029 October 1990 Forwards Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered on 901010 ML20058D0261990-10-26026 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-445/90-36 & 50-446/90-36 ML20058A7121990-10-19019 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-445/90-16 & 50-446/90-16 on 900806 ML20058A0971990-10-10010 October 1990 Forwards Insp Repts 50-445/90-31 & 50-446/90-31 on 900807- 0918 & Notice of Violation ML20062B2211990-10-0909 October 1990 Requests Response to Question Re Facility Cold Overpressure Mitigation Sys Actuation During Accident Events.Response Requested by 901214 ML20059N4711990-10-0303 October 1990 Ack Receipt of Forwarding Rev 8 to Physical Security Plan.Changes Consistent w/10CFR50.54(p) ML20059K3361990-09-17017 September 1990 Forwards Insp Repts 50-445/90-36 & 50-446/90-36 on 900820- 24 & Notice of Violation ML20059J9861990-09-13013 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Exam to Be Administered on 901010.Results of Exam Should Be Available within 3 Wks of Completion ML20059K3581990-09-13013 September 1990 Ack Receipt of 900820 Revised Response to Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57 ML20059K3561990-09-13013 September 1990 Ack Receipt of 900904 Response to Violations Noted in Insp Repts 50-445/90-22 & 50-446/90-22 ML20059J6171990-09-11011 September 1990 Forwards Insp Repts 50-445/90-30 & 50-446/90-30 on 900723- 0802.No Violations or Deviations Noted ML20059J2451990-09-10010 September 1990 Forwards Insp Repts 50-445/90-29 & 50-446/90-29 on 900723-27.No Violations Noted ML20059E2301990-08-31031 August 1990 Forwards Insp Repts 50-445/90-26 & 50-446/90-26 on 900705-0807.No Violations or Deviations Noted ML20059F3021990-08-30030 August 1990 Forwards Insp Repts 50-445/90-28 & 50-446/90-28 on 900716-20.No Violations or Deviations Noted ML20059D6511990-08-29029 August 1990 Forwards Insp Repts 50-445/90-34 & 50-446/90-34 on 900731- 0807 & Notice of Violation.Action Already Taken to Correct Hot Standby Operating Procedure Inadequacies & No Response to Violation Required ML20059D7791990-08-28028 August 1990 Forwards Investigation Synopsis Re Alleged Attempt to Inhibit Employee from Bringing Safety Concerns to Nrc. Investigation Completed in Apr 1990 ML20056B2681990-08-22022 August 1990 Advises That 881130,890313,0526 & 0920 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss Acceptable ML20059A5891990-08-15015 August 1990 Ack Receipt of 900730 Response to Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19 ML20058M2271990-08-0606 August 1990 Forwards Insp Repts 50-445/90-16 & 50-446/90-16 on 900423-27.Unresolved Item Identified.Inspector Determined That Key Emergency Response Personnel Not Always Proficient in Some Duties ML20058M2441990-08-0303 August 1990 Forwards Insp Repts 50-445/90-22 & 50-446/90-22 on 900606-0703 & Notice of Violation.Written Response Requested Based on Specifics Contained in Notice ML20056A1741990-07-30030 July 1990 Advises That Written & Operating Licensing Exams Scheduled for Wk of 901126.Licensee Should Furnish Ref Matl Listed in Encl 1 by 900904 ML20055J1481990-07-27027 July 1990 Forwards Performance Assessment Repts 50-445/90-20 & 50-446/90-02 on 900529-0615.Startup Test Program Conducted in Safe & Prof Manner & Facility Operation Could Proceed Above 50% Power ML20056A1161990-07-27027 July 1990 Forwards Summary of 900717 Meeting in Region IV Ofc Re Const Restart for Unit 2.List of Attendees & Viewgraphs Also Encl ML20055J4311990-07-26026 July 1990 Advises That 900601 Rev 7 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Portions of Plan Administrative in Nature & Do Not Reduce Plan Effectiveness ML20056A0441990-07-25025 July 1990 Grants Temporary Waiver of Compliance from Tech Specs 3.3.2 & 3.6.2.1 Re Containment Spray Sys in Order to Repair & Test Containment Pressure Transmitter 1-PT-0934 W/Unit in Hot Standby ML20055G8701990-07-20020 July 1990 Forwards Insp Repts 50-445/90-23 & 50-446/90-23 on 900618-22.No Violations or Deviations Noted ML20055G7671990-07-20020 July 1990 Ack Receipt of in Response to 900705 Telcon Re Acceptability of THERMO-LAG Fire Barrier Matl.Correspondence Reviewed & Matter Closed ML20055G0541990-07-13013 July 1990 Forwards Insp Repts 50-445/90-24 & 50-446/90-24 on 900618-22 & 25-28.No Violations or Deviations Identified ML20056A0051990-07-11011 July 1990 Advises That NRC Draft Document Re Concerns Associated W/ Util 891229 Response to Insp Repts 50-445/89-60 & 50-446/89-60 Being Placed in Pdr.Opinions in Draft Do Not Constitute Final Agency Position ML20055E8231990-07-0909 July 1990 Advises of Maint Team Insp Scheduled for Wks of 901015,29 & 1105 at Plant & Confirms Telcon Between to Mckernon & T Hope Re Insp.Team Plans to Hold Meeting W/Util at Plant Site on 901002-04 to Define Scope of Insp.List of Matls Needed Encl ML20055E4871990-07-0303 July 1990 Expresses Appreciation for Volunteering to Participate in Emergency Response Data Sys (Erds).Implementation of ERDS Will Prove to Be Beneficial to Both NRC & Util.Survey Designed to Provide Hardware & Communications Info Encl ML20055D4201990-06-29029 June 1990 Forwards Insp Repts 50-445/90-19 & 50-446/90-19 on 900503-0605 & Notice of Violation.Util Should Review Strike Contingency Plans or Procedures to Assure That Appropriate Plans in Place Before Next Strike Negotiation Deadline ML20055C7611990-06-15015 June 1990 Concludes That Plant Equipment,Program & Personnel Performance Adequate & That Testing Program Can Continue Above 50% Power Plateau to full-power,per Insp Repts 50-445/90-20 & 50-446/90-20 to Be Issued at Later Date ML20059M8611990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248H1751989-10-0303 October 1989 Discusses Submittal of Proprietary & Copyrighted Matl W/O Proper Indication.Guidelines & Procedures to Be Followed Re Proprietary & Copyrighted Matl Provided ML20248D2341989-09-29029 September 1989 Forwards Emergency Response Guidelines (Ergs) Insp Repts 50-445/89-59 & 50-446/89-59 on 890814-25.Weaknesses & Unresolved Item Noted.Engineering Task Group Developed to Resolve Number of Engineering Items Re ERGs ML20248A6481989-09-26026 September 1989 Forwards Insp Repts 50-445/89-64 & 50-446/89-64 on 890802- 0905 & Notices of Violation & Deviation ML20247R5801989-09-26026 September 1989 Forwards Insp Repts 50-445/89-63 & 50-446/89-63 on 890802-0905.No Violations or Deviations Noted ML20248A5031989-09-26026 September 1989 Forwards Insp Repts 50-445/89-66 & 50-446/89-66 on 890802- 0905 & Notice of Violation ML20248B9591989-09-22022 September 1989 Forwards Insp Repts 50-445/89-65 & 50-446/89-65 on 890802- 0905 & Notice of Violation ML20248E2671989-09-22022 September 1989 Advises That 880517 Response to Generic Ltr 88-03, Steam Binding of Auxiliary Feedwater Pumps Satisfactory IR 05000445/19890671989-09-20020 September 1989 Forwards Insp Repts 50-445/89-67 & 50-446/89-67 on 890802- 0905 & Notice of Violation ML20247H5761989-09-14014 September 1989 Ack Receipt of & Requests Addl Info Re Rept on Events of 890423 & 0505 Re Backflow Through Auxiliary Feedwater Sys ML20247K9351989-09-14014 September 1989 Forwards Insp Repts 50-445/89-61 & 50-446/89-61 on 890724-0804.No Violations or Deviations Noted ML20247N7951989-09-14014 September 1989 Forwards Insp Repts 50-445/89-68 & 50-446/89-68 on 890814-18.No Violations or Deviations Noted 1990-09-17
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M5711999-10-20020 October 1999 Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20212L2891999-10-0101 October 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases ML20212F7481999-09-24024 September 1999 Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4 ML20212F1041999-09-23023 September 1999 Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2 ML20212E6661999-09-21021 September 1999 Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure ML20212D9111999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl ML20212A7601999-09-14014 September 1999 Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls ML20211P3761999-09-0707 September 1999 Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20211J3801999-08-27027 August 1999 Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted ML20211B2861999-08-18018 August 1999 Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise ML20211C4661999-08-18018 August 1999 Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790 ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER ML20210R2221999-08-12012 August 1999 Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy 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 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 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted ML20210D8231999-07-23023 July 1999 Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20210C3331999-07-16016 July 1999 Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses ML20209H7501999-07-15015 July 1999 Forwards Safety Evaluation on GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20209G7421999-07-0808 July 1999 Forwards SER Concluding That Licensee Individual Plant Exam of External Events Process Capable of Identifying Most Likely Severe Accidents & Severe Accident Vulnerabilities & IPEEE Met Intent of Supp 4 to GL 88-20 ML20196L0121999-07-0808 July 1999 Forwards Safety Evaluation Granting First 10-Year Interval Inservice Insp Requests for Relief B-6 (Rev 2),B-7 (Rev 2), B-12,B-13,B-14 & C-9,pursuant to Tile 10CFR50.55a(g)(6)(i) ML20196K6771999-07-0202 July 1999 Ack Receipt of & Encl Scenario for Comanche Peak Steam Electric Station Emergency Plan Exercise Scheduled for 990721-22.Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20196J4881999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid as Version 2 ML20196J0401999-06-29029 June 1999 Forwards Safety Evaluation Re Plant,Units 1 & 2 Proposed Changes to Emergency Plan ML20196E6641999-06-22022 June 1999 Forwards Insp Repts 50-445/99-11 & 50-446/99-11 on 990418- 0529.No Violations Noted.Licensee Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance & Acceptable Radiological Control ML20207H3801999-06-0909 June 1999 Forwards Insp Repts 50-445/99-08 & 50-446/99-08 on 990503-11.Violations Identified & Being Treated as Noncited Violations ML20195G3771999-06-0909 June 1999 Ack Receipt of Ltr & Encl Objectives for Comanche Peak Steam Electric Station Emergency Plan Exercise Scheduled for 990721.Based on Review,Nrc Determined That Exercise Objectives,Appropriate to Meet Plan Requirements ML20207G3291999-06-0707 June 1999 Ack Receipt of Which Transmitted Rev 27 to Comanche Peak Steam Electric Station EP Under Provisions of 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of EP No NRC Approval Required ML20207E9291999-06-0202 June 1999 Discusses 990526 Request That USNRC Exercise Discretion Not to Enforce Compliance with TS 4.8.2.1e Re Performance of Battery Performance Discharge Test,In Lieu of Battery Svc Test.Concludes Action Satisfactory & Discretion Exercised ML20207D7111999-05-28028 May 1999 Advises That Info Contained in Licensee 990514 Submittal Re License Amend Request 98-01-0 Will Be Withheld from Public Disclosure,Per 10CFR2.790. 10CFR2.790 ML20207D7011999-05-27027 May 1999 Advises That Info Contained in TU Electric 990514 Submittal (TXX-99115) Re License Amend Request 98-010 Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 990511 Application & Affidavit ML20207B7241999-05-25025 May 1999 Advises That Info Contained in Application & Affidavit 990507 (CAW-99-1333),submitting WCAP-15004,dtd Dec 1997,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20206Q0031999-05-14014 May 1999 Forwards Safety Evaluation Accepting Licensee Response to GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Steam Electric Station,Unit 1 ML20206P5961999-05-12012 May 1999 Forwards Insp Repts 50-445/99-09 & 50-446/99-09 on 990419- 23.No Violations Noted.Nrc Determined That Releases of Radioactive Waste Effluents Controlled,Monitored & Quantified Well ML20206N7061999-05-12012 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl ML20206S5841999-05-11011 May 1999 Forwards Insp Repts 50-445/99-07 & 50-446/99-07 on 990307-0417.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint & Acceptable Radiological Controls ML20206K0311999-05-0707 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 ML20206H1701999-05-0606 May 1999 Forwards Copy of Exemption & Safety Evaluation Supporting Requirement in App K to 10CFR50.Proposal Will Use New Feedwater Flow Measurement Sys to Allow More Accurate Measurement to Thermal Power ML20206K3931999-05-0505 May 1999 Ltr Contract,Task Order 41, Comanche Peak Safety System Engineering Insp, Under Contract NRC-03-98-021 ML20206G1221999-05-0303 May 1999 Discusses 981215 Request That Document, Responses & Further Clarifications to NRC Questions from 980929 Meeting, Be Withheld from Public Disclosure.Determined Information to Be Proprietary & Will Be Withheld from Public Disclosure ML20206F5711999-04-30030 April 1999 Forwards Insp Repts 50-445/99-06 & 50-446/99-06 on 990329-0402.No Violations Noted.Insp Re Focus on Radiation Protection Program Activities During Unit 2 Refueling Outage ML20206E5211999-04-27027 April 1999 Discusses GL 96-01 Issued on 960110 & TU Responses, ,970102 & 980502 for Cpses,Units 1 & 2.Determined That Submittals Provided Both Info Requested & Responses Required by GL 96-01 ML20206B3831999-04-23023 April 1999 Forwards FEMA Final Rept for 990311,Comanche Peak Steam Electric Station Medical Drill.No Deficiencies or Areas Requiring Corrective Actions Identified ML20206B5321999-04-22022 April 1999 Ack Receipt of Ltrs Dtd 970407,09 & 0204,which Transmitted Revs 6 & 7 to Safeguards Continency Plan,Rev 10 to Security Training & Qualification Plan & Rev 29 to Physical Security Plan Submitted Under Provisions of 10CFR50.54(p) ML20206A2301999-04-14014 April 1999 Refers to Public Meeting Conducted on 990329 in Glen Rose, Tx Re Results of Plant Performance Review Completed on 990211 & Transmitted to Licensee on 990319.List of Attendees Encl ML20205L8711999-04-0707 April 1999 Forwards Insp Repts 50-445/99-03 & 50-446/99-03 on 990124-0306.No Violations Were Identified.Review of Operability Evaluation Re MOVs Disclosed That Licensee Failed to Include Info About Degraded ECCS Performance ML20205L1051999-04-0606 April 1999 Informs of Completion of Review of Tuec 980312 Submittal Re GL 97-05, SG Tube Insp Techniques. No Concerns Identified with SG Insp Techniques Employed at Cpses,Units 1 & 2,that Would Indicate Noncompliance with Current Licensing Basis ML20205F9141999-04-0101 April 1999 Informs That as of 990329 Dh Jaffe Has Been Assigned as Senior Project Manager for Plant IR 05000446/19920491999-03-24024 March 1999 Discusses Concern That Postulated Fire in CR Could Create Single Hot Short in Control Circuitry of MOVs Resulting in Spurious Operation.Required Hardware Mods Implemented to Control Circuits of Affected Mov,Per Insp Rept 50-446/92-49 ML20204F3311999-03-23023 March 1999 Forwards Discussion Items for 990323 Telcon 1999-09-07
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. - . .
. MAR. 21 1988 In. Reply Refer To:
Dockets: 50-445/0L-88-01 TV Electric ATTN: Mr. W. G. Counsil Executive Vice President 400 North Olive, L.B. 81 Dallas, Texas 75201 Gentlemen:
SUBJECT:
OPERATOR LICENSING EXAMINATIONS AT COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
In a telephone conversation between Messrs. Michael A. Niemeyer, Operations Training Supervisor and John E. Whittemore, Examiner, arrangements were made for the administration of reactor operator and senior reactor license examinations at the Comanche Peak Facility during the weeks of June 6 and June 13, 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 April 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 April 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. Niemeyer has been advised of our reference material requirements.
The facility management is responsible for providin i adequate space and accomodations in order to properly conduct the wrieten examinations.
Enclosure 2, "Administration of Reactor / Senior Reac.or Operator Licensing Written Examinations," describes NRC requirements for conducting these examinations. Mr. Niemeyer 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.
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The facility staff review of the written examination will be conducted in accordance with the specifications in Enclosure 3, "Requirements for Facility Review of Written Examination." Mr. Niemeyer 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 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 provided as a further addendum to this application. In the interim, it is requested, pursuant to 10 CFR 55.11, that the applicant be exempted from this requirement, as contained in 10 CFR 55.31(a)(4).
Printed Name and Signature-Training Printed Name and Signature-Senior Coordinator Management Representative on Site 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 examination date. The format and content of this addendum should read as follows:
~._ _ . _-. . _ _ _ . _ _ _ _ __ ._. ,
. c TV Electric Addendum to NRC Form 398 Application of Facility Name Printed Name and Signature-Training }rinted 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 information 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. John E. Whittemore, Examiner at (817)860-8294 or John L. Pellet, Chiet, Operator Licensing Section, at (817)860-8159.
Sincerely,
/s L. J. Cal an. Director Division of Reactor Projects
Enclosures:
- 1. Reference Material Requirements
- 2. Written Exam Administration Requirements
- 3. Facility Review Requirements cc w/ enclosures:
TV Electric Bureau of Radiation Control ATTN: Roger D. Walker State of Texas Manager, Nuclear Licensing 1100 West 49th Street Skyway Tower Austin, TX 78756 400 North Olive Street, L.B. 81 Dallas, TX 75201 (cc cont'd next page)
TV Electric cc cont'd:
Juanita Ellis CYGNA Energy Services President - CASE ATTN: Nancy H. Williams 1426 South Polk Street Suite 390 Dallas, TX 75224 2121 N. California Blvd.
Walnut Creek, CA 94596 Renea Hicks, Esq. GDS Associates, Inc.
Assistant Attorney General Suite 720 Environmental Protection Division 1850 Parkway Place P.O. Box 12548, Capitol Station Marietta, GA 30067-8237 Austin, TX 78711-2548 U.S. Nuclear Regulatory Commission Worsham, Forsythe, Sampels ATTN: Peter Bloch and Wooldridge Administrative Judge ATTN: Robert A. Wooldridge, Esq.
Washington, D.C. 20555 2001 Bryan Tower, Suite 2500 Dallas, TX 75201 Oak Ridge National Laboratory TU Electric ATTN: Elizabeth B. Johnson ATTN: Homer C. Schmidt Administrative Judge Director of Nuclear Services P.O. Box X, Building 3500 Skyway Tower Oak Ridge, TN 37830 400 N. Olive Street, L.B. 81 Dallas, TX 75201 Dr. Kenneth A. McCollom Gibbs and Hill, Inc.
1107 West Knapp ATTN: Robert E. Ballard, Jr.
Administrative Judge Director of Projects Stillwater, OK 74075 11 Penn Plaza New York, NY 10001 Dr. Walter H. Jordan Westinghouse Electric Corporation Administrative Judge ATTH: R. S. Howard 881 West Outer Drive P.O. Box 355 Oak Ridge, TN 37830 Pittsburgh, PA 15230 Anthony Z. Roisman, Esq. Christic Institute Suite 600 ATTN: Lanny A. Sinkin 1401 New York Avenue, N.W. 1324 N. Capitol Street Washington, D.C. 20005 Washington, D.C. 20002 ,
'(cc cont'd next page)
_ _ _ - . , , _ . _ . . _ , _ _ , _ , . - . . _ . ~ . _ . . _ , , . . _ _ _ _ _ _ . .
TV Electric a
+ cc' cont'd:
Billie'Pirner Barde, Esq. Orrick, Herrington & Sutcliffe Government Accountability Project ATTN: David R. Pigott, Esq.
Midwest Office 600 Montgomery Street 104 East Wisconsin Avenue San"Francisco, CA 94111 Appleton, WI 54911 Spiegel & McDiarmid Newman & Holtzinger, P.C.
ATTN: Robert Jablon ATTN: Jack R. Newman, Esq.
Bonnie S. Blair 1615 L. Street,'N.W.
1350 New York Avenue, N.W. Washington, D.C. 20036 Washington, D.C. 20005-4798 Senior Citizens Alliance of Tarrant Fulbright & Jaworski County, Inc. ATTN: Joseph F. Fulbright.
ATTN: George A. Parker, Chairman 1301 McKinney Street Public Utility Committee Houston, TX 77010 6048 Wonder Drive Fort Worth, TX 76133 TV Electric Heron, Burchette, Ruckert, & Rothwell ATTN: Jack Redding ATTN: William A. Burchette Esq.
c/o Bethesda Licensing Counsel for Tex-La Electric 3 Metro Center, Suite 610 Cooperative of Texas Bethesda, MD 20814 Suite 700 1025 Thomas Jefferson St., N.W.
Washington, D.C. 20007 Comanche Peak Steam Electric Station ATTN: M. A. N:emeyer, Operations Training' Supervisor P.O. Box 2300 Glen Rose, TX 76043 bec to DMB (IE42) bec dist. by RIV:
RIV Files Local PDR J. Whittemore CPPD:0SP Reading (Mail Stop 7-H-17) J. Pellet CPPD Reading (HQ) Site Reading R. Martin SRI-0PS SRI-CONST RPSB-DRSS MIS System, RIV OSP (Mail Stop 7-D-24) J. Partlow RSTS Operator DRP B. Hayes L. Shea, RM/ALF J. Taylor F. Miraglia S. Ebneter/JAxelrad C. Grimes E. Jordan P. McKee J. Lyons J. Moore 0GC J. Wilson M. Malloy J. Gilliland
ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS
- 1. Existing. learning objectives and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics, etc.).
Training materials should include all substantive written material used for preparing candidates _for initial R0 and SRO licensing. The written 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 result in canceling and rescheduling of the examinations. Training materials which include the following should be provided:
o System descriptions _ including descriptions of all operationally g 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 and 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.,
reactor theory material should contain explanations how principles relate to the actual curves used 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).
- 4. All integrated plant procedures (normal or general operating procedures).
- 5. Emergency procedures (emergency instructions, abnormal or special procedures).
- 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, when appropriate).
- 8. Radiation protection manual (radiation protection manual or procedures).
- 9. Emergency plan implementing procedures.
- 10. Technical Specifications.
- 11. System operating procedures.
- 12. Piping and instrumet.tation diagrams, electrical single-line diagrams, or 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.
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 feedwater control valve).
- e. An indication of modeling conditions or problems that may impact the examination.
- f. Identification of unknown Performance 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 expose the candidates to situations of degraded pressure control (PWR), degraded heat removal capability (PWR and BWR), and containment challenges (BWR) may be provided (voluntary by facility licensee),
- i. Simulator instructors manual (voluntary by facility licensee).
- j. Description of the scenarios used for the training class (voluntary by facility licensee).
- 16. Additional material required by the examiners to develop examinations that meet the requirements of these standards and regulations.
The above reference material should be approved, final issues, 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 agreement 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.
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 Item 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 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 Specifications, 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. All other reference material needed to complete the examination shall be furnished by the examiner. Candidates may bring pens, pencils, nonprogramable calculators, or slide rules into the examination room. No other equipment or reference material shall be allowed.
- 5. Only black ink or dark pencils should be used for writing answers to questions.
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s e .
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 facility licensee will have five (5) working days from the day the
. ritten 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. Commentsnotsubmittedwithinfive(5)workingdays 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 formal comments are received and resolved. If the formal comments are not received by the deadline the final examination results may be 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:
- a. NRC question number
- b. Facility licensee comment
- c. Copy of supporting documentation (the reference may be cited if the document is held by the Operator Licensing Section)
NOTES: 1. No change to the examination will be made without submittal of, or proper reference to, complete, current, and approved reference material.
- 2. Comments made without a clear, concise, facility licensee recommendation, will not be addressed.
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