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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
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4 e' ,.
t JUL 301990 In Reply Refer To:
Docket: 50-285 l
' Omaha Public Power District '
ATTN: W. G. Gates, Division Manager Nuclear Operations 444 South 16th Street Mall Mail Stop 8E/EP4'
- Omaha, Nebraska- 68102-2247 Gentlemen:-
SUBJECT:
LICENSillG EXAMINATIONS AT OMAHA PUBLIC POWER DISTRICT }
In a telephone conversation between Mr. R. T. Ridenoure of your staff and ;
Mr. J. E. Whittemore, ilRC Chief Examiner for your facility, arrangements were i made for the administration of licensing examinations at the Fort Calhoun l Station.
The written examinations are scheduled for November 13, 1990. The operating examinations are scheduled for November 14 and 15, 1990.
To meet the above schedule it will be necessary for you to furnish the reference material listed in Enclosure 1, " Reference Material Requirements for Reactor / Senior Reactor Operator Licensing ~ Examinations," by September 17,1990. Any delay in receiving approved, properly bound and indexed reference material or the-submittal of-inadequate or incomplete reference material may result in the examination being rescheduled. Mr. Ridenoure has been advised of our reference material requirements, and the address where each set of. reference material is to be mailed. 1 You are responsible for providing adequate space and accommodations for administration of the written examinations. Enclosure 2 " Requirements for Administration of Written Examinations," describes our requirements for conducting these examinations. Mr. Ridenoure has also been informed of these requirements.
Enclosure 3 contains-the NRC Rules and Guidelines that will:be in effect during the. administration of the written-examination. The facility management is responsible for ensuring that all applicants are aware of these rules. '
The facility staff review of the written examinations will-be conducted in s accordance with requirements specified in Enclosure 4, " Requirements for facility Review of-Written Examinations." Mr. Ridenoure has been informed i of these requirements.
RIV:0LS* C:0LS* D:DRS h - . RS :DRP JWhittemore/cjg- JPellet LJCa) Tan .ABB ch . SJCollins
/ /90 / /90 / //p/90 0 7 /.27/90- ,
- previously concurred 9008060034 90073o PDR v ADOCK c5000285 A poc 7 t l
i Omaha Public Power District -?- I l
To document simulator examinations effectively, the Chief Examiner will have j the simulator operator record predetermined plant conditions (i.e., plant pressure, temperature, pressurizer level, etc.) for each simulator scenario.
The applicants will be responsible for providing this information with any appeal of simulator operating examination. Therefore, your training staff-should retain the original simulator examination scenario information until all applicants who.took examinations have passed the operating examination, accepted the denial of their license, or filed an appeal.
Preliminary reactor operator and senior reactor operator license applications should be submitted to reach this office at least 30. days bef ore the first '
examination date 50 that we will be able to review the training and experience of the candidates, prosess the medical certifications, and prepare final examiner assignmtnts af ter applicant eligibility has been determined. If the applications are not received at least 30 days before the examination date, it is likely that a postponement will be necessary. Final signed applications certifying that all traininn has been completed shall be submitted at least 14 days before the first ex$mination date.
This request is covered by Office of llanagement and Budget Clearance ,
ilumber 3150-0101 which expires May 31, 1992. The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, copying and mailing the required material. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Information and Records fianagement Branch, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Comission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0101), Office of Management and Budget, Washington, D.C. 20503.
Thank you for your consideration in this matter. If you have any questions regarding the examination procedures and requirements, please contact ,
Mr. J. L. Pellet, Chief, Operator Licensing)
Mr.J.Whittemore,ChiefExaminer,at(817 Section, at (817) 860-8159 or 860-8294.
Sincerely, Cggind Syne $ B0 p P.Gwynn Samuel J. Collins, Director Division of Reactor Projects
Enclosures:
- 1. Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinetions
- 2. Requirements for Administration of Written Examinations i
- 3. HRC Rules and Guidelines for Written Examinations
- 4. Requirements for Facility Review of Written Examinations
9i' l Omaha Public Power District ,
1 ccw/ enclosures: l LeBoeuf,. Lamb,-Leiby & MacRae l ATTN: Harry H. Voigt, Esq. l 1333 New Hampshire Avenue, NW l Washington, D.C. 20036 Washington County Board ;
of Supervisors ' l ATTH: Jack Jensen, Chairman Blair, Nebraska 60008 Combustion Engineering, Inc. .
ATTH: Charles B. Brinkman, Manager '!
Washington Nuclear Operations 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852-Department of Health ATTN: Harold Borchert. Director Division of Radiological Health 301 Centennial M:11, South P.O. Box 95007 Lincoln, Nebraska 68509 Fort Calhoun Station G. R. Peterson, Manager
-ATTH: ,
P.O. Box 399 Fort Calhoun.. Nebraska 68023 i
U.S. Nuclear' Regulatory Connission-l ATTN: Resident Inspector P.O. Box 309 4 Fort Calhoun .Hebraska 68023 U.S. Nuclear Regulatory Commission ATTN: Regional Administrator, Region IV '
611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Omaha Public Power District l ATTH: J. K. Gasper, Manager l Training l 444-South 16th Street Mall Omaha, Nebraska- 68102-2247 I l
l 1
l
L Omaha Public Power District bectoDMB(IE42)_
bec to distrib. by RIV: !
R. D. Martin, RA Sectionchief(DRP/C) i MIS System RIV File DRS(J.L.PelletReadingFile)- J. L. Pellet E. Himes L. Miller, TTC P. O'Connor, ilRR Project Henager (HS: 13-D-18)
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Licensee & Debt Collection Branch, ATTH: Leah Tremper ,
J. Whittemore- -
J. Whittemore Reading File ;
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ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR /SEllIOR REACTOR OPERATOR LICENSIllG EXAMINATIONS t
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Existinglearning(objectives,JobPerformanceMeasures,studenthandoutr*
and lesson plans including training manuals, plant orientation manual, 3
system descriptions, reactor theory, thermodynamics, etc.).
A copy of the facility Job 'and Tesk Analysis -(JTA), specifying the .
knowiedges and abilities required of an operator at the facility. Each 1 particular knowledge and/or ability will include an importance rating correlating it to ensuring the health and safety of the public. If a JTA is not furnished, the Knowledges and Abilities Catalog for Nuclear Power Plant Operators, NUREG 1122 (1123) will-be used to establish content .
validity for the examination.
All Job Performance Measures (JPMs) used to ascertain the competence of the operators in performing tasks within the control room complex and, as ,
identified in the facility JTAs, outside of the control room, i.e., local operations.
Training materials shall include all substantive written material used for preparing applicants for initial R0 and SR0 licensing. The written material shall include learning objectives and the details presented during lectures, rather than outlines. Training materials shall be identified by plant and unit, bound, and indexed.' FAILURE TO PROVIDE COMPLETE, PROPERLY B0UND AND INDEXED PLAtlT REFERENCE MATERIAL llAY RESULT-IN.THE RETURN OF THE MATERIAL TO THE PERSON WHO IS THE HIGHEST LEVEL 0F '
CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G., VICE-PRESIDENTOFNUCLEAROPERATIONS). ACCOMPANYING THE MATERIAL WILL BE A COVER LETTER EXPLAltlING THE DEFICIENCIES Ill THE REFERENCE MATERIAL AND THE FACT THAT THIS WAS THE REASON THE EXAllIllATIONS WERE CANCELLED OR POSTPONED. Training materials which include the following shall 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 procedures used for operating the applicable system.
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.
Training material used to clarify and strengthen. understanding of emergency operating procedures.
- 2. CompleteProcedureIndex(includingsurveillanceprocedures,etc.)
-3. Alladministrativeprocedures(asapplicabletoreactoroperationor safety)
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- 4. Allintegratedplantprocedures(normalorgeneraloperatingprocedures)
- 5. Emergency procedures (emergency instructions, abnormal or special procedures) :
- 6. Standing orders (important orders that are safety-related and ray supersedetheregularprocedures)
- 7. Surveillanceprocedures(proceduresthatarerunfrequently,i.e., weekly orthatcanberunonthesimulator)
- 8. Fuel-handling and core-loading procedures, (initial core-loading procedure,whenappropriate)
- 9. All annunciator / alarm procedures
- 10. Radiationprotectionmanual(radiationcontrolmanualorprocedures)
- 11. Emergency plan implementing procedures
- 12. TechnicalSpecifications(andinterpretations,ifaveilable)forallunits for which licenses are sought
-13. System operating procedures
- 14. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams
- 15. Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and setpoints (PLS) for the facility
- 16. Questions and answers specific to the facility training program which may be used in the written or operating examinations (voluntary by f acility licensee).
- 17. The following material for the plant reference simulation facility:
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- a. List of all preprogramed initial conditions [
- b. List of all preset malfunctions with a clear identification number.
The~1ist shall 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 shall be provided. Additionally, an indication of which annunciators are to be initially expected shall be given. i
l 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 malfR ction should be provided, i.e., ;
ability to vary the size of a giv'en LOCA or ster.m leak, or the l 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 identification of modeling conditions / problems that may impact the examination
- f. Identification of any known' performance test dicerepancies not yet corrected
- g. Identification of differences between the simulator and the reference plant's control room
- h. Copies of facility generated scenarios that expose the ap'licants a to-situations of decreased capability (PWR:and BWR) pressure control leat removaland (PWR),
containnent degraded(PWR and B challenges ;
be provided (voluntary by licensee)
. i. Simulator instructor's manual (voluntary by licensee)
- j. Description of the scenarios used for the training class (voluntary by licensee)
- 18. Additional material required by the examiners to develop examinations that meet the requirements.of NUREG 1021, Operator Licensing Examiner Standards and the regulations.
The above reference material shall be approved, final' issues and shall be so >
marked. If a plant has not finalized some of the material, the Chief Examiner shall verify with the facility that the most complete, up-to-date material is available and that agreement has been reached with the licensee for limiting changes before the administrat wn of the examination.- All; procedures and ,
reference material-shall be bound with appropriate indices or tables of-contents so that they can be used effi'ciently. Failure to provide complete, (properly bound and~ indexed plant reference material could result in cancellation or rescheduling of the exaininations, o
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L ENCLOSURE 2 REQUIREMENTS FOR ADtilNISTRATION OF WRITTEN EXAMINATIONS l
- 1. A single room shall be provided for administration of the written- l examination. The location of this room and supporting restroom facilities ;
shall be such as~ to prevent contact with all other facility and/or contractor personnel during the written examination. If necessary, the facility should make arrangements for the use of a suitable room at a local school, motel, or other building. Obtaining this room-is the responsibility of the-licensee.
- 2. Minimum spacing is required to ensure examination integrity as determined by the Chief Examiner. . Minimum spacing should be one applicant per table, with a 3-foot space between tables. ,
- 3. Suitable arrangements shall be made by the facility if the applicants are '
4 to have lunch, coffee, or other refreshments. These arrangements shall ,
comply with Item 1 above and shall be reviewed by the examiner and/or i proctor.
- 4. The facility licensee shall provide pads of 8 1/2. by 11-inch lined paper in unopened packages for each applicant's use in completing the examination. The examiner shall distribute these pads to.the applicants.
- 5. ~. Applicants may bring pens, pencils, calculators, or slide rules into the examination room. Only black ink or dark pencils- should be used for writing answers to questions.
- 6. The licensee shall provide one set of steam tables-for each applicant.
The proctor shall distribute the steam tables to the applicants. No wall ,
charts, models, and/or other training materials shall be present-in-the examination room. No other equipment or reference material shall be allowed unless provided by the proctor.
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ENCLOSURE 3 PROCEDURES FOR' T.;E ADMlHISTRATI0fl 0F WRITTEN EXAP.INATIONS
- 1. Check identification badges. ;
2.- Pass out examinations and all handouts. Remind applicants not to review ;l examination until instructed to do so..
READ THE FOLLOWING INSTRUCTIONS VERBATIM:
'During the administration of this examination the f0110 wing rules apply:
l 1. Cheating on the examination means'an automatic denia1 of your application and could result in more severe penalties.
- 2. After'the examination has been completed, you must sign the statement on >
the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be
.done after you= complete the examination.
READ THE FOLLOWING INSTRUCTIONS:
- 1. Restroom trips are to be limited and only one applicant 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.
- 2. Use black ink or dark pencil only to facilitate legible reproductions.
- 3. Print your name in the blank provided in the upper right-hand corner of the examination-cover sheet and each answer sheet.
- 4. Mark your answers'on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND 00 NOT' WRITE ON THE BACK SIDE OF THE PAGE.
- 5. Before you turn in your examination, consecutively number each answer -
sheet, incit. ding any additional pages inserted when writing your answers on'the examination question page.
- 6. . Use abbreviations only if they are commonly used in facility-literature. !
Avoid using symbols such as < or > signs to avoid a simple. transposition error resulting in'an. incorrect answer. Write it out.
- 7. .The point value for each question is indicated in parentheses after the question.
- 8. Show all calculations, methods, or assumptions used to obtain an answer to any short answer questiP:.
- 9. Partial! credit may be given except on multip1'e choice questions.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER-DLANK.
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- 10. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of- ,
1.00 even though you got the four correct answers.
- 11. If the intent of a question is unciear, ask questions of the examiner only.
- 12. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.
- 13. Ensure all information you wish to have evaluated as part of your answer. -
is on your answer sheet. Scrap paper will be disposed of imediately-
.following the examination.
- 14. To pass the examination, you must achieve a gracie of 80% or greater.
- 15. There is a time limit of four (4) hours for completion of the examination.
- 16. When you are done and have turned in your examination ~, leave the .
exeminitionarea(DEFINETHEAREA). If you are found in this area while l
I the examination is still in progress, your license may be denied or revoked.
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4 ENCLOSURE 4 i r
REQUIREMENTS FOR FACILITY REVIEW Of WRITTEN EXAMINATIONS ,
- 1. At the option of the Chief Examiner, the facility may review the written examination up to two weeks prior to its administration. This review may take place at the facility or in the Regional office. The review will be conducted using the same material sent to the NRC for examination generation. purposes.! The Chief Examiner will coordinate the details of-the review with the facility. An NRC examiner will always be-available during the review.
Whenever this option of examination review is utilized, the facility !
reviewers shall sign the.following statement prior to being allowed access.
to the examination. The examination or written notes will not be retained~~
by the facility,
, a. Pre-Examination Security Agreement I _
acknowledge.that I~have acquired specialized knowledge concerning the examination scheduled for at.
as of the date of my signature below. I agree that I will not knowingly divulge any information concerning this (
examination to any unauthorized persons. 1 understand that I am not to participate in any instruction involving those applicants scheduled to be administered the above examination from this date i until after the examination has been administered. I further -
understand that violation of the conditions of this agreement may>
result in the examination being cancelled and/or enforcement action against myself or the facility licensee by whom I am employed or represent. 4 i
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In addition, the facility staff reviewers will sign the following
. statement after the written examination has been= administered.;
- b. Post-Examination Security Agreement
, I did not, to the best of my knowledge, divulge' any information concerning the. examinations administered during the week of at to any unauthorized i persons. I did not participate in providing any instruction.to those applicants who were administered the examination from the date I entered into this security agreement until the.' completion'of examination administration.
. Signature /Date d
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- 2. Regardless of whether the above examination review option is exercised, imediately following the administration of the written examination, the facility staff shall be provided a marked up copy of the examination and the answer key. The copy of the written examination shall include pen and ink changes made to questions during the examination administration.
If the facility did not review the examination prior to its administration, they will have five (5) working days from the day of the written examination.to submit formal coments. If the facility reviewed the examination prior to its administration, any additional coments must be given to an examiner prior to his/her leaving the site at the end of the week of the written examination administration. In either case, the coments will be addressed.to the responsible Regional office by the highest level of corporate management for plant operations, e.g., Vice President for Nuclear Operations. A copy of the-submittal will be forwarded to the Chief Examiner, as appropriate.. Coments not submitted <
within the required time frame will be considered for inclusion in the grading process on a case-by-case basis by the Regional Office Section Chief. Should the comment submittal deadline not be met, a long delay in grading the examinations may occur.
- 3. The following format should be adhered to for submittal of specific coments: .
- a. Listing of-NRC question, answer and reference
- b. Facility coment/recomendation
- c. Reference (to support facility coment)
NOTES: 1. No change to the examination will be made without submittal of a reference to support the facility comment. Any supporting documentation that was not previously supplied, should be L provided.
- 2. Coments made without a concise facility recommendation will not l be addressed.
- 4. A two hour post-examination review may be held at the discretion of the Chief Examiner. If this review is held, the facility staff should be informed that only written coments that are properly supported will be considered in the grading of the' examination.
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