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Category:CORRESPONDENCE-LETTERS
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999 Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached ML20217G9261999-10-15015 October 1999 Forwards Insp Rept 50-285/99-10 on 990913-17.One NCV Noted ML20217G2331999-10-14014 October 1999 Forwards Insp Rept 50-285/99-09 on 990913-17.No Violations Noted LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999 Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999 Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls ML20217B5111999-10-0606 October 1999 Forwards Amend 193 to License DPR-40 & Safety Evaluation. Amend Revises TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance require- Ments for RCS Flow Rate ML20216H7231999-09-29029 September 1999 Informs That Util 980325 Response to GL 97-06, Degradation of SG Internals, Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Fort Calhoun Station,Unit 1 ML20212L9571999-09-27027 September 1999 Informs That Follow Up Insp for Drill/Exercise Performance Indicator Will Be Conducted During Wk of 991001 LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999 Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999 Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999 Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999 Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999 Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters IR 05000285/19990081999-09-0707 September 1999 Forwards Insp Rept 50-285/99-08 on 990907-0811.No Violations Noted.Insp Consisted of Exam of Activities Conducted Under License as Relate to Safety & to Compliance with Commission Rules & Regulations & with Conditions of License ML20211P2581999-09-0303 September 1999 Forwards Insp Rept 50-285/99-06 on 990809-12.No Violations Noted.Insp Consisted of Exam of Activities Under License as Related to EP & to Compliance with Commission Rules & Regulations & with Conditions of License LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999 Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase ML20211J9231999-09-0202 September 1999 Forwards SE Accepting Licensee 990301 Requests for Relief Re Third 10-year ISI Interval for Plant,Unit 1.Relief Proposed Alternatives to Requirements in ASME B&PV Section XI,1989 Edition,Paragraphs IWA-5242(a) & IWA-5250(a)(2) ML20211L3241999-09-0202 September 1999 Informs That Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) of Amend 192 to License DPR-40 Issued on 990727.Corrected Page Encl LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999 Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld ML20211F4491999-08-25025 August 1999 Forwards Ltr from Ja Miller,Dtd 990819,which Notified State of Iowa of Deficiency Identified During 990810,Fort Calhoun Station Biennial Exercise.One Deficiency Identified for Not Adequately Demonstrating Organizational Capability LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d) LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999 Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld ML20210R1491999-08-13013 August 1999 Forwards Insp Rept 50-285/99-07 on 990719-23.No Violations Noted.Nrc Identified One Issue Which Was Evaluated Under Risk Significance Determination Process & Was Determined to Be of Low Risk Significance LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required 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 ML20210N1991999-08-0909 August 1999 Informs That as Result of NRC Review of Licensee Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210P8991999-08-0909 August 1999 Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999 Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable 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 LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999 Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331 LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999 Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program ML20210G1851999-07-27027 July 1999 Forwards Amend 192 to License DPR-40 & Safety Evaluation. Amend Consists of Changes to TS in Response to 990129 Application LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999 Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630 ML20216D6951999-07-26026 July 1999 Informs That During 990614 Review of Fort Calhoun,Nrc Noted That Drill/Exercise Performance Indicator Has Entered White Band,Which Indicated Level of Licensee Performance That Warranted Increased Regulatory Response LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999 Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999 Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld ML20210D9471999-07-22022 July 1999 Forwards Amend 191 to DPR-40 & Safety Evaluation.Amend Authorizes Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20210C0201999-07-20020 July 1999 Informs That Due to Administrative Oversight,Revised TS Bases Provided in to Fort Calhoun Station Were Not Dated.Dated Pages to TS Encl ML20210B0761999-07-19019 July 1999 Forwards Insp Rept 50-285/99-05 on 990601-0710.No Violations Noted ML20209G5351999-07-15015 July 1999 Informs That Staff Incorporated Rev of TS Bases Provided by Licensee Ltr Dtd 980904,into Fort Calhoun Station Tss. Staff Finds Revs to Associated TS Bases to Be Acceptable. Revised Bases Pages Encl ML20209F5741999-07-12012 July 1999 Ack Receipt of Transmitting Exercise Scenario for Upcoming Biennial Offsite Exercise Scheduled 990810.Scenario Reviewed & Acceptable ML20209G5591999-07-0808 July 1999 Forwards Detailed Listing of Staff Concerns with C-E TR NPSD-683,rev 3 & RCS pressure-temperature Limits Rept LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999 Forwards Fort Calhoun Performance Indicators Rept for May 1999 LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999 Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld ML20209D8771999-07-0101 July 1999 Summarizes 990630 Public Meeting Conducted in Fort Calhoun, Ne Re Results of Completed Culture Survey,Plant Status, Facility Activities Re New NRC Oversight Process & License Renewal.Licensee Handout & Attendance List Encl LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999 Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G6561990-11-19019 November 1990 Forwards Amend 134 to License DPR-40 & Safety Evaluation. Amend Addresses Two Administrative Changes ML20216K0541990-11-14014 November 1990 Forwards Safety Evaluation Denying Request for Exemption from Requirements of 10CFR50,App R for Fire Area 34B for Wide Range Nuclear Power Instrumentation Channels.Required Level of Protection Not Provided ML20062E4641990-11-0909 November 1990 Forwards Insp Rept 50-285/90-42 on 901015-19.No Violations or Deviations Noted ML20058H0551990-11-0101 November 1990 Forwards List of Unimplemented Gsis,Per Generic Ltr 90-04 ML20058C6821990-10-24024 October 1990 Offers No Comment on Annual Exercise Scenario Submitted Via ML20058A3901990-10-19019 October 1990 Advises That Maint Team Reinspection Scheduled for Wks of 901203 & 10.Meetings Will Be Scheduled on 901113-14 in Preparation for Insp.List of Required Matls Encl ML20062B6041990-10-12012 October 1990 Forwards Amend 133 to License DPR-40 & Safety Evaluation. Amend Modifies Tech Spec to Increase Refueling Boron Concentration & Revise Storage Requirements of Spent Fuel Pool Region 2 ML20059N3311990-09-28028 September 1990 Forwards Final SALP Rept 50-285/90-24 for Period of May 1989 - Aug 1990.Actions Discussed in 900726 SALP Mgt Meeting & Util 900827 Response to Initial SALP Rept Considered to Be Responsive to NRC Concerns & Recommendations ML20059M6751990-09-28028 September 1990 Forwards Insp Rept 50-285/90-35 on 900729-0910.No Violations or Deviations Noted ML20059K7061990-09-14014 September 1990 Disagrees W/Position That More Detailed Design & Safety Assessment Using Ipe/Pra Appropriate Framework,Per Generic Ltr 89-19 ML20059K3691990-09-14014 September 1990 Ack Receipt & Review of Changes to Emergency Plan Re Emergency Facilities & Equipment Based on Review of .Proposed Changes Acceptable ML20059J9871990-09-13013 September 1990 Provides Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 901010.W/o Map of Exam Area & Preliminary Instructions to Participant Encl ML20056B4071990-08-20020 August 1990 Forwards Insp Rept 50-285/90-34 on 900730-0803.No Violations or Deviations Noted.Unresolved Items Identified in Paragrphs 2.1 & 4.0 of Encl Insp Rept ML20059A2211990-08-17017 August 1990 Forwards Evaluation of Cen 387-P, Pressurizer Surge Line Thermal Stratification. Info Provided by C-E Owners Group in Ref 1 & 2 Inadequate to Justify Meeting All Appropriate Limits for 40-yr Plant Life ML20058M8071990-08-10010 August 1990 Discusses Closeout of NRC Bulletin 90-001, Loss of Fill-Oil Transmitters Mfg by Rosemount. Util Replaced Four Transmitters Which Fell within Scope of Bulletin During Refueling & Maint Outage ML20058N3711990-08-10010 August 1990 Advises That Programmed Enhancements for Generic Ltr 88-17, Loss of DHR, Acceptable ML20056A5761990-08-0707 August 1990 Forwards Request for Addl Info to Review Alternate Seismic Criteria & Methodologies for Facility ML20056A7551990-08-0606 August 1990 Advises of Concluded Investigation Case 4-87-016 Re Alleged False Welding Records,Violations of Employee Protection & Cheating on Welding Performance Tests.Allegations Unsubstantiated ML20056A1721990-07-30030 July 1990 Advises That Written Licensing Exams Scheduled on 901113 & Operating Licensing Exams Scheduled on 901114 & 15.Licensee Requested to Furnish Ref Matl Listed in Encl 1 by 900917 in Order to Avoid Exam Being Rescheduled ML20056A3461990-07-27027 July 1990 Summarizes 900724 Meeting W/Util in Region IV Ofc Re Changes to Operator Licensing Program ML20055J1461990-07-23023 July 1990 Forwards Insp Rept 50-285/90-30 on 900513-0616 & Notice of Violation.App C Withheld from Public Per 10CFR73.21 ML20055G1791990-07-18018 July 1990 Ack Receipt of Advising NRC of Corrective Actions in Response to Violations Noted in Insp Rept 50-285/90-13. Implementation of Actions Will Be Reviewed During Future Insp ML20055G3931990-07-16016 July 1990 Informs That Financial Info Submitted for 1990 in Util Satisfies 10CFR.140 Requirements ML20055F6841990-07-12012 July 1990 Forwards Initial SALP Rept 50-285/90-24 for May 1989 - Apr 1990 IR 05000285/19900021990-07-0909 July 1990 Ack Receipt of 900507 & 0629 Responses to Violations & Deviations Noted in Insp Rept 50-285/90-02 ML20055G0171990-07-0606 July 1990 Forwards Amend 132 to License DPR-40 & Safety Evaluation. Amend Changes Tech Spec Pages 5-1,5-5,5-8 & 5-9a to Incorporate Title Changes as Result of Reorganization & Partial Relocation of Emergency Planning Dept IR 05000285/19900291990-07-0505 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-285/90-29 ML20055C7901990-06-18018 June 1990 Forwards Insp Rept 50-285/90-26 on 900416-0512.Violations Noted.No Citations Issued for Violations Discussed in Paragraphs 5.a,5.b, & 5.c of Rept ML20055C8051990-06-15015 June 1990 Forwards Insp Rept 50-285/90-25 on 900402-06 & 16-19 & Notice of Violation.Violations Pertain to Inadequate Assessment Aids,Detection Aids,Compensatory Measure & Key Control ML20059M9681990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C4101990-02-23023 February 1990 Advises That 891010 & 1207 Changes to Emergency Plan Reviewed by Emergency Preparedness Staff & Acceptable ML20248C7421989-09-28028 September 1989 Forwards Insp Rept 50-285/89-32 on 890801-31.Noted Violations Not Being Cited to Encourage & Support Util self-identification & Correction of Problems.One Unresolved Item Discussed in Paragraph 7.a of Rept ML20248C4901989-09-22022 September 1989 Forwards Summary of 890828 Enforcement Conference in Arlington,Tx to Discuss Violations Noted in Insp Repts 50-285/89-10 & 50-285/89-31.Attendance List Also Encl ML20247Q6361989-09-21021 September 1989 Forwards Amend 8 to Indemnity Agreement B-67,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements IR 05000285/19890011989-09-19019 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-285/89-01.NRC Will Withdraw Items 3 & 4 If Review of Safety Evaluation Documentation Found to Be Adequate ML20247L2491989-09-18018 September 1989 Advises That 890907 Meeting W/Util Re Status of Plant Safety Enhancement Program Provided for Better Understanding of Progress Util Made in Implementing Program.List of Attendees & Meeting Slides Encl ML20247L6161989-09-0606 September 1989 Advises That 890808 Priority Description & Interim Milestones for Rev of safety-related Procedures & Commitment to Final Completion Date of 901231 Acceptable.Nrc Should Be Notified If Interim Milestones Cannot Be Met ML20247A3151989-08-30030 August 1989 Forwards Final SALP Rept 50-285/89-19 for May 1988 - Apr 1989,summary of 890713 Meeting to Discuss SALP Rept & Util 890817 Response to SALP Rept ML20247B1611989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executives Meeting on 890818 in Arlington,Tx.Topics Discussed Included Improving Communications,Salp Process in Region IV & Enforcement.List of Attendees & Agenda Encl ML20247B4191989-08-29029 August 1989 Forwards Insp Rept 50-285/89-28 on 890701-31.No Violations or Deviations Noted.One Unresolved Item Identified ML20246F0161989-08-25025 August 1989 Forwards Insp Rept 50-285/89-30 on 890724-28.No Violations or Deviations Noted ML20246D5521989-08-23023 August 1989 Discusses Util Response to Generic Ltr 89-08, Erosion/ Corrosion-Induced Pipe Wall Thinning, & Advises That Licensee Maintain,In Auditable Form,Records of Program ML20246E0791989-08-18018 August 1989 Discussess Insp Repts 50-285/89-10 & 50-285/89-23 on 890227-0303 & 0508-10 & Forwards Notice of Violation. Decision Not Reached by NRC Re Failures to Adequately Protect Safeguards Info from Compromises,Per 10CFR73.21 ML20246A0531989-08-17017 August 1989 Forwards Supplemental Safety Evaluation for Rev 4 to Inservice Testing Program for Pumps & Valves,Per Generic Ltr 89-04 ML20245H8901989-08-15015 August 1989 Forwards Safety Evaluation Supporting Util 890215 Response to Generic Ltr 83-28,Item 2.1 (Part 1), Vendor Interface for Reactor Trip Sys Components ML20245K3431989-08-11011 August 1989 Forwards Safety Evaluation Determining That Isolation Devices Qualified & Acceptable for Interfacing Safety & Nonsafety Sys Re Implementation of ATWS Rule 1990-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G9261999-10-15015 October 1999 Forwards Insp Rept 50-285/99-10 on 990913-17.One NCV Noted ML20217G2331999-10-14014 October 1999 Forwards Insp Rept 50-285/99-09 on 990913-17.No Violations Noted ML20217B5111999-10-0606 October 1999 Forwards Amend 193 to License DPR-40 & Safety Evaluation. Amend Revises TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance require- Ments for RCS Flow Rate ML20216H7231999-09-29029 September 1999 Informs That Util 980325 Response to GL 97-06, Degradation of SG Internals, Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Fort Calhoun Station,Unit 1 ML20212L9571999-09-27027 September 1999 Informs That Follow Up Insp for Drill/Exercise Performance Indicator Will Be Conducted During Wk of 991001 IR 05000285/19990081999-09-0707 September 1999 Forwards Insp Rept 50-285/99-08 on 990907-0811.No Violations Noted.Insp Consisted of Exam of Activities Conducted Under License as Relate to Safety & to Compliance with Commission Rules & Regulations & with Conditions of License ML20211P2581999-09-0303 September 1999 Forwards Insp Rept 50-285/99-06 on 990809-12.No Violations Noted.Insp Consisted of Exam of Activities Under License as Related to EP & to Compliance with Commission Rules & Regulations & with Conditions of License ML20211L3241999-09-0202 September 1999 Informs That Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) of Amend 192 to License DPR-40 Issued on 990727.Corrected Page Encl ML20211J9231999-09-0202 September 1999 Forwards SE Accepting Licensee 990301 Requests for Relief Re Third 10-year ISI Interval for Plant,Unit 1.Relief Proposed Alternatives to Requirements in ASME B&PV Section XI,1989 Edition,Paragraphs IWA-5242(a) & IWA-5250(a)(2) ML20211F4491999-08-25025 August 1999 Forwards Ltr from Ja Miller,Dtd 990819,which Notified State of Iowa of Deficiency Identified During 990810,Fort Calhoun Station Biennial Exercise.One Deficiency Identified for Not Adequately Demonstrating Organizational Capability ML20210R1491999-08-13013 August 1999 Forwards Insp Rept 50-285/99-07 on 990719-23.No Violations Noted.Nrc Identified One Issue Which Was Evaluated Under Risk Significance Determination Process & Was Determined to Be of Low Risk Significance 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 ML20210P8991999-08-0909 August 1999 Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill ML20210N1991999-08-0909 August 1999 Informs That as Result of NRC Review of Licensee Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 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 ML20210G1851999-07-27027 July 1999 Forwards Amend 192 to License DPR-40 & Safety Evaluation. Amend Consists of Changes to TS in Response to 990129 Application ML20216D6951999-07-26026 July 1999 Informs That During 990614 Review of Fort Calhoun,Nrc Noted That Drill/Exercise Performance Indicator Has Entered White Band,Which Indicated Level of Licensee Performance That Warranted Increased Regulatory Response ML20210D9471999-07-22022 July 1999 Forwards Amend 191 to DPR-40 & Safety Evaluation.Amend Authorizes Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation ML20210C0201999-07-20020 July 1999 Informs That Due to Administrative Oversight,Revised TS Bases Provided in to Fort Calhoun Station Were Not Dated.Dated Pages to TS Encl ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20210B0761999-07-19019 July 1999 Forwards Insp Rept 50-285/99-05 on 990601-0710.No Violations Noted ML20209G5351999-07-15015 July 1999 Informs That Staff Incorporated Rev of TS Bases Provided by Licensee Ltr Dtd 980904,into Fort Calhoun Station Tss. Staff Finds Revs to Associated TS Bases to Be Acceptable. Revised Bases Pages Encl ML20209F5741999-07-12012 July 1999 Ack Receipt of Transmitting Exercise Scenario for Upcoming Biennial Offsite Exercise Scheduled 990810.Scenario Reviewed & Acceptable ML20209G5591999-07-0808 July 1999 Forwards Detailed Listing of Staff Concerns with C-E TR NPSD-683,rev 3 & RCS pressure-temperature Limits Rept ML20209D8771999-07-0101 July 1999 Summarizes 990630 Public Meeting Conducted in Fort Calhoun, Ne Re Results of Completed Culture Survey,Plant Status, Facility Activities Re New NRC Oversight Process & License Renewal.Licensee Handout & Attendance List Encl ML20196F4931999-06-24024 June 1999 Discusses 990617 Public Meeting at Dana College,Blair,Ne Re Overview of Pilot Insp Program ML20196D2321999-06-21021 June 1999 Forwards Corrected Cover Ltr for Insp Rept 50-285/99-04. Original Cover Ltr Incorrectly Stated That Rept Contained Two Noncited Violations,When Rept Actually Documented Only One ML20195J2121999-06-14014 June 1999 Ack Receipt of Ltr Dtd 990316,which Transmitted Rev 16B to Site Security Plan,Rev 2 to Safeguards Contingency Plan & Rev 6 to Training & Qualification Plan for Plant,Under Provisions of 10CFR50.54(p) IR 05000285/19990041999-06-11011 June 1999 Corrected Ltr Forwarding Insp Rept 50-285/99-04 on 990425-0531.Insp Determined That One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation, Consistent with App C of Enforcement Policy ML20195J2481999-06-11011 June 1999 Forwards Insp Rept 50-285/99-04 on 990425-0531.Violations Identified & Being Treated as Noncited ML20195G3141999-06-10010 June 1999 Ack Receipt of & Encl Objectives for Facility Emergency Plan Exercise,Scheduled for 990810 ML20195E8391999-06-0909 June 1999 Ack Receipt of Transmitting Changes to Licensee Emergency Plan,Rev 14 & Emergency Plan Implementing Procedure OSC-1 Under Provisions of 10CFR50,App E,Section IV ML20207G4741999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station EP Implementing Procedure EPIP-OSC-1, Emergency Classification,Rev 31,under Provisions of 10CFR50, App E,Section V ML20207G4631999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station Ep,App B,Rev 4,under Provisions of 10CFR50,App E,Section V.No Violations Identified During Review ML20207G2981999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station Radiological Er Plan,Section E,Rev 22,under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required Due to Determination That Effectiveness Unchanged ML20207G4661999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station EP Implementing Procedure EPIP OSC-1, Emergency Classification,Rev 30,under Provisions of 10CFR50, App E,Section V ML20195G3621999-06-0808 June 1999 Ack Receipt of ,Which Transmitted Changes to Fort Calhoun Station Emergency Plan,App A,Rev 15,under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required ML20207G3401999-05-27027 May 1999 Informs That NRC Held Planning Meeting on 990511 for Fort Calhoun Station to Identify Insp Activities at Facility for Next 6 to 12 Months.Informs of NRC Planned Insp Activities & Offers Licensee Opportunity to Provide Feedback ML20207A9041999-05-24024 May 1999 Informs That NRR Reorganized,Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Was Created. Reorganization Chart Encl ML20206U6331999-05-18018 May 1999 Forwards Insp Rept 50-285/99-03 on 990314-0424.Four Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20206L4151999-05-10010 May 1999 Forwards SE of OPPD Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20206H4471999-05-0707 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 ML20206E7201999-04-28028 April 1999 Responds to Meeting Conducted 990419 in Fort Calhoun,Ne Re Results of PPR Completed 990211.Addl Topics Discussed Included New Assessment Process & Upcoming Actions Planned in Response to Y2K Concerns ML20205Q5671999-04-15015 April 1999 Forwards Amend 190 to License DPR-40 & Safety Evaluation. Amend Revises TS 5.2.f & TS 5.11.2 to Change Title of Shift Supervisor to Shift Manager ML20205J2751999-04-0202 April 1999 Forwards Insp Rept 50-285/99-02 on 990131-0313.No Violations Noted.During Insp,Licensee Conduct of Activities at Fort Calhoun Station Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices ML20205A7191999-03-19019 March 1999 Informs That on 990211 NRC Staff Completed PPR of Fort Calhoun Station.Review Was Conducted for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20207K6151999-03-11011 March 1999 Forwards Insp Rept 50-285/99-01 on 990208-26.One Noncited Violation Was Identified ML20207E8691999-03-0303 March 1999 Forwards Correction to Amend 188 to License DPR-40 for Plant,Unit 1.Administrative Error,Three Pages of TSs Contained Errors,An Incorrect Page Number,Missing Parenthesis & Misspelled Words ML20203F2041999-02-11011 February 1999 Informs That During 990208 Telcon Between Mc Ralrick & J Pellet & T Stetka,Arrangements Were Made for Administration of Licensing Examinations at Fort Calhoun Station for Week of 991018 1999-09-07
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APR 2 51988 In Reply Refer To:
Docket: 50-285/0L-88-03 Omaha Public Power District ATTN: R. L. Andrews, Division Manager-Nuclear Production 1623 Harney Street Omaha, Nebraska 68102 Gentlemen:
SUBJECT:
OPERATOR LICENSING EXAMINATIONS AT FORT CALHOUN STATION (FCS)
During a telephone conversation between Messrs J. Fluehr, Supervisor, Station .
Training, and J. Pellet, Chief, Operator Licensing Section, arrangements were made for the administ ation of reactor operator and senior operator license ,
examinations at FCS auring the week of July 25, 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 f acility, by May 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 May 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. Fluehr has been advised of our reference material requirements.
The facility management is responsible for providing adequate space and accommodations 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. Fluehr 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.
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. Fluehr has been informed of these requirements.
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Omaha Public Power District 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:
i Addendum to NRC Form 398
! Application of Facility Name i
i Printed Name and Signature-Training Printed Name and Signature-Senior Coordinator Management Representative on Site j This is to certify that has successfully completed the j
licensee requirement for licensing, as required under 10 CFR 55.31(a)(4).
l Omaha Public Power District 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 Mr. John L. Pellet, Chief, Operator Licensing Section, at (817)860-8159.
Sincerely, 9
Original Signed By.
Il }, Callan L. J. Callan, Director Division of Reactor Projects l
Enclosures:
- 1. Reference Material Requirements
- 2. M tten Exam Administration Requirements
- 3. Facility Review Requirements cc w/ enclosures:
Fort Calhoun Station ATTN: W. G. Gates, Manager
- P.O. Box 399 I Fort Calhoun, Nebraska 68023
! Harry H. Voigt Esq.
- LeBoeuf, Lamb. Leiby & MacRae
! 1333 New Hampshire Avenue, NW Washington, D. C. 20036 l
J. Fluehr Supervisor, Station Training P.O. Box 399 Fort Calhoun, Nebraska 68023 J. Gasper, Manager, Administration and Training Services P.O. Box 399 Fort Calhoun, Nebraska 68023 l
! Kansas Radiation Control Program Director l Nebraska Radiation Control Program Director l
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R.D. Martin, RA RPSB-DRSS Section Chief (DRP/B) MIS System
.RIY File ~ DRP S. McCrory .
Project. Engineer,DRP/B Lisa-Shea,RM/ALF _
T. Bournia NRR Project Manager DRS H. Scott, Acting EO TSS RRI E. Haycraft J. Pellet t
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. i ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR i
, OPERATOR LICENSING EXAMINATIONS l
- 1. Existing learning objectives and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics,etc.). j Training materials should include all substantive written material used t for preparing candidates for initial R0 and SR0 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: '
System descriptions including descriptions of all operationally relevant flow paths, components, controls and instrumentation. ,
System training material should draw parallels to the actual i procedures used for operating the applicable system. j Complete and operationally useful descriptions of all safety-system l interactions, and, where available, B0P system interactions under i emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure. ,
Training material used to clarify and strengthen understanding of !
- emergency operating procedures.
Comprehensive theory material that includes fundamentals in the area i of theory of reactor operation, thermodynamics, heat transfer, and :
fluid flow, as well as specific applications to actual in-plant !
components. For examp1_e, mechanical theory material should include pump theary 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 'imits followed in the plant (e.g., "
reactor theory material should contain explanations of how principles l
relate to the actual curves used by operators to verify shutdown j margin or calculate an ECP).
- 2. Procedure Index (alphabetical by subject). ,
- 3. Alladministrativeprocedures(asapplicabletoreactoroperationor 4 safety).
4 All integrated plant procedures (normal or general operating procedures).
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- 5. Emergency procedures (emergency instructions, abnormal, or special procedures). [
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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.
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- 10. Technical Specifications.
- 11. System operating procedures.
- 12. Piping and instrumentation 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 upon 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 ma feedwater control valve)jor valve (e.g., drifting shut of a main
- e. An indication of modeling conditions or problems that may impact the examination,
- f. Identification of unknown Performance Test failures not yet completed.
l 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 degraded
, and containment chal heatremovalcapability(vo(PWRandBWR)pressurec (BWR)may-beprovided luntary 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).
- 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 issued, 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 restroom 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 81/2- by 11-inch lined paper it; 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, non-programable 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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- I NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination, the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may ;
leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions.
4 Print your name in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write only one side of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example,1.4, 6.3, etc.
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are comonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial Pedit may be given. Therefore ANSWER ALL PARTS OF THE QUESTION.
DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
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- 18. When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.-
-(3) Answer pages including figures which are a part'of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions..
- c. Turn in'all scrap paper and the balance of the paper that you did not use for answering the questions,
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your' license may be denied or revoked.
ENCLOSURE 3 I
REQUIREMENTS FOR FACILITY REVIEW OF WRITTEN EXAMINATIONS i
- 1. There shall be no review of the written examination by the facility i 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 f acility licensee will have 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 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 formal t conments 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 i slot.
- 3. The following information shall be provided for each individual comment:
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- a. NRC question number 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) +
t 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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