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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:INCOMING CORRESPONDENCE
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
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
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
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
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
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
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-99-0075, 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
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
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
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-99-0057, 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
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
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
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
LIC-99-0061, Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl1999-06-30030 June 1999
Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl
LIC-99-0056, Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-061999-06-22022 June 1999
Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-06
LIC-99-0059, Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning1999-06-22022 June 1999
Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning
LIC-99-0054, Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 9908101999-06-0808 June 1999
Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 990810
LIC-99-0052, Forwards Fort Calhoun Station Performance Indicators, for Apr 19991999-06-0202 June 1999
Forwards Fort Calhoun Station Performance Indicators, for Apr 1999
LIC-99-0045, Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl1999-05-26026 May 1999
Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl
LIC-99-0046, Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise1999-05-12012 May 1999
Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise
LIC-99-0028, Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage1999-04-30030 April 1999
Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage
LIC-99-0036, Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F1999-04-28028 April 1999
Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F
LIC-99-0043, Forwards Fort Calhoun Performance Indicators Rept for Mar 19991999-04-28028 April 1999
Forwards Fort Calhoun Performance Indicators Rept for Mar 1999
LIC-99-0041, Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager1999-04-27027 April 1999
Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager
LIC-99-0037, Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue1999-04-26026 April 1999
Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue
LIC-99-0039, Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a1999-04-20020 April 1999
Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a
LIC-99-0038, Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl1999-04-20020 April 1999
Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl
LIC-99-0033, Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps1999-04-15015 April 1999
Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps
LIC-99-0035, Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure1999-04-0808 April 1999
Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure
LIC-99-0031, Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate1999-03-31031 March 1999
Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate
LIC-99-0032, Forwards Fort Calhoun Station Performance Indicators, for Feb 19991999-03-31031 March 1999
Forwards Fort Calhoun Station Performance Indicators, for Feb 1999
LIC-99-0029, Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques1999-03-30030 March 1999
Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques
LIC-99-0027, Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld1999-03-16016 March 1999
Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld
LIC-99-0022, Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl1999-03-12012 March 1999
Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl
LIC-99-0024, Informs That OPPD Withdraws Applications Submitted by 950626 &1999-03-12012 March 1999
Informs That OPPD Withdraws Applications Submitted by 950626 &
LIC-99-0016, Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives1999-03-0101 March 1999
Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives
LIC-99-0023, Forwards FCS Performance Indicators for Jan 19991999-03-0101 March 1999
Forwards FCS Performance Indicators for Jan 1999
LIC-99-0020, Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included1999-02-24024 February 1999
Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included
LIC-99-0011, Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 11999-02-0505 February 1999
Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 1
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARLIC-90-0705, Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl1990-09-17017 September 1990
Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl
LIC-90-0745, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions1990-09-17017 September 1990
Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions
LIC-90-0717, Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-071990-09-13013 September 1990
Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07
LIC-90-0716, Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls1990-09-13013 September 1990
Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls
LIC-90-0740, Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits1990-09-12012 September 1990
Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits
LIC-90-0741, Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets1990-09-0707 September 1990
Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets
LIC-90-0440, Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes1990-09-0606 September 1990
Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes
LIC-90-0667, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 9005291990-09-0404 September 1990
Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 900529
LIC-90-0712, Forwards fitness-for-duty Program Performance Data for Period of Jan-June 19901990-08-31031 August 1990
Forwards fitness-for-duty Program Performance Data for Period of Jan-June 1990
LIC-90-0683, Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations1990-08-27027 August 1990
Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations
LIC-90-0627, Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection1990-08-22022 August 1990
Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection
LIC-90-0670, Forwards Fort Calhoun Station Performance Indicators for Jul 19901990-08-22022 August 1990
Forwards Fort Calhoun Station Performance Indicators for Jul 1990
LIC-90-0662, Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution1990-08-22022 August 1990
Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution
LIC-90-0673, Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl1990-08-22022 August 1990
Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl
LIC-90-0636, Forwards Results of 1990 Refueling Outage Inservice Insp & Rept for Repairs or Replacement1990-08-13013 August 1990
Forwards Results of 1990 Refueling Outage Inservice Insp & Rept for Repairs or Replacement
LIC-90-0591, Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-21990-08-13013 August 1990
Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-2
LIC-90-0631, Responds to Generic Ltr 89-15 Re NRC Solicitation of Utils to Voluntarily Participate Emergency Response Data Sys Program.Util Prepared to Work W/Nrc to Investigate Actions Necessary to Implement Program at Plant1990-08-0808 August 1990
Responds to Generic Ltr 89-15 Re NRC Solicitation of Utils to Voluntarily Participate Emergency Response Data Sys Program.Util Prepared to Work W/Nrc to Investigate Actions Necessary to Implement Program at Plant
LIC-90-0485, Confirms Interim Resolution of Identified Problem Associated W/Use of Input Variable for PORV Opening Time in Calculation of Low Temp Overpressure Protection Sys Setpoints1990-08-0707 August 1990
Confirms Interim Resolution of Identified Problem Associated W/Use of Input Variable for PORV Opening Time in Calculation of Low Temp Overpressure Protection Sys Setpoints
LIC-90-0645, Forwards Application for Amend to License DPR-40,making Typo & Administrative Corrections to Tech Specs1990-08-0202 August 1990
Forwards Application for Amend to License DPR-40,making Typo & Administrative Corrections to Tech Specs
LIC-90-0647, Informs That Tl Patterson Assumed Position of Plant Manager, Effective 9008011990-08-0101 August 1990
Informs That Tl Patterson Assumed Position of Plant Manager, Effective 900801
LIC-90-0659, Advises of Plans to Achieve Operability of Third Auxiliary Feedwater Pump by 9008101990-07-31031 July 1990
Advises of Plans to Achieve Operability of Third Auxiliary Feedwater Pump by 900810
LIC-90-0449, Forwards Rev 1 to EA-FC-90-037, Control Room Habitability Evaluation for NUREG-0737,Item III.D.3.41990-07-20020 July 1990
Forwards Rev 1 to EA-FC-90-037, Control Room Habitability Evaluation for NUREG-0737,Item III.D.3.4
LIC-90-0588, Provides Notification of SPDS Implementation at Plant,Per1990-07-19019 July 1990
Provides Notification of SPDS Implementation at Plant,Per
LIC-90-0585, Forwards Simulator Malfunction Cause & Effects1990-07-18018 July 1990
Forwards Simulator Malfunction Cause & Effects
ML20055D9351990-07-0202 July 1990
Forwards Fort Calhoun Station Performance Indicators,May 1990
LIC-90-0564, Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility1990-06-29029 June 1990
Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility
LIC-90-0522, Forwards Revised Response to Notice of Deviation from Insp Rept 50-285/90-02.Corrective Actions:Cable Trays 5-4A & 5-4B Reworked to Neatly Tie Down Cables & Remove Crossovers & Engineering Instruction GEI-9 on Electrical Sys Updated1990-06-29029 June 1990
Forwards Revised Response to Notice of Deviation from Insp Rept 50-285/90-02.Corrective Actions:Cable Trays 5-4A & 5-4B Reworked to Neatly Tie Down Cables & Remove Crossovers & Engineering Instruction GEI-9 on Electrical Sys Updated
LIC-90-0566, Forwards 1990/1991 Statement of Cash Flow from Operations. Cash Flow Statement Deviates from Reg Guide 9.4 Due to Util Being Political Subdivision of State of Ne1990-06-29029 June 1990
Forwards 1990/1991 Statement of Cash Flow from Operations. Cash Flow Statement Deviates from Reg Guide 9.4 Due to Util Being Political Subdivision of State of Ne
LIC-90-0488, Responds to Request for Info Re Status of Implementation of Generic Safety Issue Requirements1990-06-29029 June 1990
Responds to Request for Info Re Status of Implementation of Generic Safety Issue Requirements
LIC-90-0446, Forwards Application for Amend to License DPR-40,to Restrict Containment Spray Use as Backup for Shutdown Cooling in Tech Specs1990-06-28028 June 1990
Forwards Application for Amend to License DPR-40,to Restrict Containment Spray Use as Backup for Shutdown Cooling in Tech Specs
LIC-90-0429, Forwards Application to Amend License DPR-40,adding Hydrogen Purge Sys to Tech Spec.Discussion,Justification & NSHC Analysis for Amend,Provided1990-06-28028 June 1990
Forwards Application to Amend License DPR-40,adding Hydrogen Purge Sys to Tech Spec.Discussion,Justification & NSHC Analysis for Amend,Provided
ML20043J0611990-06-22022 June 1990
Responds to NRC 900523 Ltr Re Violations Noted in Insp Rept 50-285/90-29.Corrective Actions:Five Chemistry Technicians Provided Refresher Training on 900427 on Existing EPIP-EOF-6
ML20044A1631990-06-22022 June 1990
Requests That NRC Continue Processing Exemption Request for Configuration of wide-range Nuclear Instrumentation Cables in Fire Area 34B (Upper Electrical Penetration Room). Emergency Boration Added to Achieve Safe Shutdown
ML20044A4961990-06-18018 June 1990
Forwards Supplemental Application for Amend to License DPR-40,making Administrative Corrections to Tech Specs. Procedure SO-G-70, Chemical Control Also Encl
ML20043G2981990-06-14014 June 1990
Provides Followup to Special Rept on Inoperable Fire Barriers.Eight Inoperable Dampers Replaced Under Mod MR-FC-87-036, Fire Damper Replacement. Remaining 38 Dampers Found to Be Acceptable After Damper Design Review
ML20043E6451990-06-0808 June 1990
Provides Supplemental Response to Generic Ltr 88-17 & NRC Bulletin 80-12.Plant Pumps & Suction Header Piping Not Originally Constructed for Use as Backup to LPSI Sys for Shutdown Cooling
ML20043E0071990-06-0101 June 1990
Discusses Rev to Previous Commitments Made in Response to Requirements of 10CFR50,App R,Section Iii.G Re post-fire Repairs to Equipment Required for Cold Shutdown Following Fire in Fire Area 6
ML20043G3281990-06-0101 June 1990
Advises That Personnel at Util Reviewed Reactor Operator Licensing Exam Administered on 900529.Comments on Exam Encl
ML20043C1811990-05-29029 May 1990
Advises That Util Has Cleaned RW HXs AC-1A & AC-1D & Will Clean AC-1C by 900615
ML20043B4981990-05-24024 May 1990
Updates Schedule for Submitting Results of PORV Block Valve Prototype Testing.Establishment of Test Parameters & Development of Test Procedures Tentatively Scheduled for Submittal in Nov 1990.Final Rept Expected by 910630
ML20043B5061990-05-23023 May 1990
Advises That Testing to Verify Operability of Hydrogen Purge Sys Successfully Completed During 1990 Refueling Outage.Proposed Tech Spec Rev Will Be Submitted by 900701
ML20043B4731990-05-23023 May 1990
Forwards Fort Calhoun Station Performance Indicators, Monthly Rept for Apr 1990
ML20043A7821990-05-18018 May 1990
Advises That Licensee Plans to Replace Valves HCV-247 & HCV-2988 During 1991 Refueling Outage Pending Successful Redesign & Retesting of New Valves by Valcor
ML20043A8021990-05-18018 May 1990
Advises That Walkdown of safety-related Portions of Plant to Verify Accuracy of Fire Barrier Penetration Drawings & Surveillance Tests Will Be Completed by 900831
ML20043B0391990-05-16016 May 1990
Informs of Current Status of Post Accident Sampling Sys. Program Meets Min Requirements & Fulfills Conditions of Tech Spec 5.15
ML20042G9861990-05-11011 May 1990
Forwards Rev 0 to Interim Operability Criteria (Ioc) Criteria for Performing Safety Analysis for Interim Operability of Piping, Resulting from Discussion at 900306 & 0418 Meetings
ML20042G9571990-05-10010 May 1990
Forwards Suppl to Application for Amend to License DPR-40, Making Administrative Clarification to Chloride Sampling Requirements.Standing Order Procedure S.O.-M-10, Tool Accountability Also Encl
ML20042G9981990-05-10010 May 1990
Forwards Proprietary & Nonproprietary Rev 13 to EPIP-EOF-18, Offsite Radiological Surveys.
ML20042H0021990-05-10010 May 1990
Fowards Fort Calhoun Station Performance Indicators,Mar 1990, Monthly Rept
ML20042G4671990-05-0909 May 1990
Forwards Application for Amend to License DPR-40,changing Chemical & Vol Control Sys
1990-09-07
[Table view] |
Text
o . .
Omaha Public Power District 1623 HARNEY e O M A H A, NE8RASMA 68102 e TELEPHONE S36 4000 AREA CODE 402 July 25, 1980 Mr. Paul F. Collins, Chief Operator Licensing Branch U. S. Nuclear Regulatory Comission Washington, D. C. 20555
Reference:
Docket No. 50-285
Dear Mr. Collins:
The Omaha Public Power District received a letter from the Com-mission, dated March 23, 1980, regarding the qualification of reactor operators. In response to Item A.2 of Enclosure (1) to the Comission's letter, attached hereto for your review is a copy of the revised Fort Calhoun Station Operations Department Training Program for licensed operators.
Sincerely,
/ f/O)
W. C/ Jones Division Manager Production Operations WCJ/KJM/BJH/PRT:jmm Attachment cc: U. S. Nuclear Regulatory Comission Office of Inspection & Enforcement Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenae, N. W.
Washington, D. C. 20036 poO3 5
/!/
8 0 08120 n., s 79 O
C. DEPARTMENTAL TRAINING 1.0 Operations Department Initial Training Persons assigned to the Operations Department who are not licensed as Senior Operators or Reactor Operators by the Nuclear Regulatory Commission shall participate in the Training Program for Licensing Senior / Reactor Operator Candidates.
This training program is described in detail in Appendix B.
When a trainee has completed the Training Program for Licensing Senior / Reactor Operator Candidates, he will be recommended to sit for a Nuclear Regulatory Commission license examination.
When a Nuclear Regulatory Commission license is granted to a trainee, he will immediately begin to participate in the Licensed Operator Requalification Program.
1.1 Responsibilities 1.1.1 The Training Coordinator will schedule and
- document the Training Program for Licensing Senior / Reactor Operator Candidates. He will assist the Operations Supervisor in the evalu-ation of the progress of license candidates.
When a candidate is ready to sit for a Nuclear Regulatory Commission License, he will prepare the license application. The training coordinator will review all completed plant modifications, additions and Plant Review Committee minutes for significant items (current operating history, problems, procedure changes and administrative limits) applicable to training.
-- - , n, c- - , , , - - , , - - , - - - .
1.1 Rasponsibilitisc (continu;d) 1.1.1 (continued)
The infor=ation obtained will be disseminated to training instructors by the training coor-dinator.
1.1.2 Training instructors who lecture on systems, integrated responses and transients shall possess a Senior Operating License. Such lectures presented by a person without a Senior Operating License shall be proctored by an individual with a Senior Operating License.
1.1.3 The Supervisor-operations vill ensure that operational personne'l participate in the Operations Department Initial Training and will monitor and evaluate the progress of license candidates. He vill ady^.se the Manager - Fort Calhoua Station when license candidates have completed the Training Program for Licensing Senior / Reactor Operator Candidates and are ready to sit for Nuclear Regulatory Commission license examinations.
1.1.h The Division Manager - Production Operations vill transmit license applications to the Nuclear Regulatory Coc: mission and vill certify that the applicant has been trained to operate the controls of the reactor in a safe and competent manner and has need of a Reactor Operator or a Senior Reactor Operator License for the performance of his duties.
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a e 1.2 Documentation Each person participating in the Training Program for Licensing Senior / Reactor Operator Candidates will com-plete the system checkouts, practical factors and on-the-job training of the Operator's Training Study Guide and Record and will maintain the record of his progress. The Operator's Training Study Guide and Record is Appendix C of this manual.
The Training Coordinator will prepare a training file for each candidate containing a record of videotape lecture attendance and outline completion, a record of lecture attendance and all quizzes and avaminations, records of drills performed, experience factors and simulator training certifications.
1.3 Schedules An annual schedule for the Operations Department will be published containing the planned training events for the participants in the Training Program for Licensing Senior / Reactor Operator Candidates.
2.0 Operations Department Retraining All members of the Operations Department who hold Nuclear Regulatory Commission Reactor Operator or Senior Reactor Operator Licenses will participate in the Licensed Operator i Requalification Program which is a continuous training program over a two year period and includes annual requalification examinations, preplanned lectures, simulator training and on-i the-job training. The Licensed Operator Requalification Program is described in detail in Appendix D of this manual.
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4
t b 2.1 Rasponsibilities 2.1.1 The Trainint aordinator shall schedule and docu=ent the Licensed Operator Requalification.
The Training Coordinator vill prepare a training file for each licensed operator and =aintain a record of participation on the Requalification Training Suman for=s (Appendix H). The 4
Training Coordinator vill prepare, ad=inister, and grade the Annual Requalificatica Exa=ination and prepare the annual Operations Depart =ent training schedule using the results of the Annual Requalification Exa=ination to select the topics for the pre-planned lecture series.
2.1.2 Training instructors who lecture on syste=s, integrated responses and transients shall possess a Senior Operating License. Such lectures presented by a person without a Senior Operating License shall be proctored by an individual with a Senior Operating Lictnse.
2.1.3 The Supervisor-operations vill ensure that Operations personnel participate in Operations Department Retraining and vill evaluate the perfor=ance of licensed operators annually.
2.1.h The Manager - Fort Calhoun Station vill review the annual evaluation of licensed operators.
2.2 Schedule An annual schedule for the Operations Department will be published containing the planned training events for the participants in the Licensed Operator Requalification Training Progra=.
APPENDIX B TRAINING PROGRAM FOR LICENSING SENIOR / REACTOR OPERATOR CANDIDATES a
Omaha Public Power District Fort Calhoun Station Unit No. 1 Training Program for Licensing Senior / Reactor Operator Candidates A. PURPOSE 1.0 The purpose of the Fort Calhoun Station Unit No.1 Training Program for Licensing Senior / Reactor Operator Candidates is to provide a training program for those individuals who are in pursuit of Senior or Reactor Operator Licenses as defined by the Code of Federal Regulations 10CFR55 B. RESPONSIBILITY 1.0 It is the responsibility of the Plant Manager through the training coordinator to ensure that the Training Program for Licensing Senior / Reactor Operator Candidates as established herein is administered.
C. APPLICABILITY 1.0 All personnel in pursuit of Senior or Reactor Operator Licenses for the Fort Calhoun Station Unit No. 1 are required to com-plete the training program described herein.
2.0 a) Personnel in pursuit of a Senior Reactor Operator License shall have a minimum of a high school diploma or equiva-lent and 4 years of responsible power plant experience.
Responsible power plant experience should be that ob-tained as a control room operator (fossil or nuclear) or as a power plant staff engineer involved in the day-to-day activities of the facility. A maximum of 2 years power plant experience may be fulfilled by academic or related technical training, on a one-for-one time basis.
Two years shall be nuclear power plant experience. At least 6 months of the nuclear power plant experience shall be at the Fort Calhoun Station.
b) App?icants for Senior Operator Licenses shall have held an vperator's License for 1 year.
30 Personnel in pursuit of a Reactor Operator License shall have a high school diploma or equivalent and two years of power plant experience of which a minimum of one year shall be nuclear power plant experience.
D. DEFINITIONS 1.0 Operating Personnel - those personnel assigned to the shift operating crew, i.e., Shift Supervisors, Equipment Operators -
Nuclear, Auxiliary Operators - Nuclear and Helpers.
D. DEFINITIONS (continued) 2.0 Supervisory Personnel - those individuals not normally assigned to the shift operating crew, i.e., Plant Manager, Technical Supervisor and other staff personnel.
3.0 A reactivity change shall be defined as any of the following operations:
- a. Changing plant condition from Hot Shutdown to Hot Standby and power escalation to the point of adding heat.
- b. Changing plant conditions from Hot Standby to Min 4= =
Load (15% power).
- c. Increasing plant load by an amount equal to or greater than 10% power.
- d. Decreasing plant load by an amount equal to or greater than 10% power.
- e. During power operation, trade off boron reactivity for control element reactivity for a reactivity change of at least 0.1%dk/k.
- f. Xenon transient follow provided transient is significant enough to require adjustment of boron concentration.
- g. Changing plant condition from Minimum Load (15% power) to Hot Standby.
- h. Reactor trip.
- i. Reactor trip recovery.
E. SCOPE 1.0 This licensing program sets forth the requirementc which must be met by the license candidate prior to his NRC examination. j 2.0 In addition, the program extablishes the methods to be utilized for:
l a. Scheduling training assignments.
l l b. Evaluating the progress of license candidates.
. c. Documenting the participation of license candidates.
I l F. TRAINING PROGRAM 1.0 The training program for all license candidates shall consist of the following requirements:
- a. License candidates shall complete the Video Tape Lecture i Series. The lecture series consists of video tapes which j address the following topics:
l
1".
F. TRAINING PROGRAM (continued)
(1) Module 1: Nuclear Power Orientation (2) Module 2: Basic Nuclear Concepts (3) Module 2: Basic Nuclear Concepts Chart of the Nuclides (15)
(4) Module 3: Reactor Operation Steam Tables (15)
(5) Module 4: Plant Performance (6) Module 5: Radiation Protection Code of Fed. Reg.10 (15)
(7) Module 6: Water & Waste Treatment (8) Module 7: Instrum. & Op. Analysis Each video tape is accompanied by a lecture outline, a study guide and problems.
- b. License candidates in pursuit of a Reactor Operator License shall complete the Auxiliary Operator Study Guide and Record, the Equipment Operator Study Guide and Record, and the Reactor Operator Study Guide and Record as specified by the Operator's Training Study Guide and Record.
Reactor Operator applicants shall have 3 months training on shift as an extra person in the control room. In addition to the above, those license candidates in pur-suit of a Senior Operator License shall complete the Shift Supervisor's Study Guide and Record as specified by the Operator's Training Study Guide and Record. SRO candidates shall have 3 months of shif t training as an extra man on shift.
- c. License candidates shall:
(1) Complete two (2) reactor startups at Fort Calhoun Station Unit No. 1, OPTION I, or j (2) manipulate the controls of the reactor during five (5) significant reactivity changes, OPTION II. The reactivity changes may or may not include reactor startups. -
OPTION I will require the license candidate to perform a reactor startup as part of his NRC operoting test.
OPTION II will require the license candidate to partici-pate in a simulator training program. If this option is utilized, the license candidate will not be required to perform a reactor startup as part of his NRC operating test. The simulator training program shall provide
- sufficient simulator training to ensure that the. license candidate is
- - - n , - - , - - - -
a .-
. . l F. TRAINING PROGRAM (continued)
(a) able to manipulate the controls and keep the reactor under control during a reactor startup.
(b) able to predict instrument response and the use of instrumentation during a reactor startup, (c) able to follow'the facility startup procedure and (d) able to explain alarms and annunciators that may occur during the reactor startup.
If a simulator is required, the Combustion Engineering pressurized water reactor simulator at Windsor, Connecticut will be used. The Combustion Engineering simulator re-
' produces the general operating characteristics of Fort Calhoun Station Unit No. 1. The general arrangement of the instrumentation and controls of this simulator are similar to Fort Calhoun Station Unit No.1.
d
- d. Lectures will be given to license candidates and will include the following topics:
(1) Theory and Principles of Operation (2) General and Specific Plant Operating Characteristics (3) Plant Instrumentation and Control Systems (4) Plant Prc.ection Systems (5) Engineered Safety Systems (6) Normal and Emergency Operating Procedures (7) Radiation Control and Safety (S) Technical Specifications (9) Quality Assurance for Operations (10) Heat Transfer, Fluid Flow and Thermodynamics (11) Use of Installed Plant Systems to Control or Hitigate Accident: Involving Severe Core Damage (12) Reactor and Plant Transients C. SCHEDULING 1.0 Video tape lecture and Study Guide assignments for Operating Personnel shall be scheduled in the Shift Training Package.
2.0 Lectura assignments for license candidates shall be scheduled on the Weekly Training Schedule.
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H. EVALUAT'Of 1.0 Periodic quizzes and tests vill be given to all video tape lecture series participants. Failure on these quizzes and tests is a grade of less than 805.
2.0 The simulator training center must attest to the applicants:
- a. Ability to nantpulate the controls and keep the reactor under control during'a reactor startup,
- b. Ability to predict instrument response and use the instrumentation during a reactor startup,
- c. Ability to follow the facility startup procedure and
- d. Ability to explain alar =s and annunciittors that may occur during this operation.
3.0 Periodic quizzes vill be given to all lecture studies partici-pants to evaluate their. knowledge in topics covered by the lectures. Failure on these quizzes is a grade of less than 805.
h.0 Reactivity manipulations and reactor startups vill be evaluated on the Experience Factor Record by Senior Operator Licensed Personnel.
5.0 Failure on any examination given to Operating or Supervisory Personnel vill be a grade of less than 80%.
I. DOCUMFliTATION 1.0 The following records shall be maintained to document each license candidate's participation in the Training Progras for Licensing Senior / Reactor Operator Candidates.
- a. Video tape lecture attendance and a copy of each quiz and test administered.
- b. Conpleted Experience Factor Records for Operating and Supervisory Personnel.
- c. Co=pleted Operator's Training Study Guide and Record manuals.
- d. Lecture attendance and a copy of each quiz administered.
- e. Simulator training center certification of training.
- f. A copy of all examinations given to Operating and Super-visory Personnel.
2.0 The records described above vill be maintained as required by the Fort Calhoun Station Unit No.1 Technical Specifications.
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Simulator Training Program for Senior / Reactor Overator License Candidates Simulator training for Fort Calhoun Station Unit No.1 Senior / Reactor Operator License candidates will be conducted at the Combustion Engineering Nuclear Training Facility in Windsor, Connecticut.
The simulator training program vill provide additional hands-on exp *ien;;e and reactor startup opportunities. The hands e n experience vill cousist of demonstration sessions, practice sessions and exercise or evaluation sessions.
Demonstration sessions vill be used initially to demonstrate nor=al plant operation, then to demonstrate plant transients and accidents. The license candidates vill have an opportunity to operate the plant controls under a variety of conditions both with and without plant malfunctions.
Arexercise session vill be utilized to evaluate the license candidates '
operational ability during reactor startups.
COURSE SYLLABE Training Session Duration
- 1. Pre-Simulator Classroom Lectures 2 Days
- a. Rex?. tor Coolant System
- b. Chemical and Volume Control Systems
- c. Turbine Generator
- d. Steam, Feedvater and Condensate System
- e. Reactor Regulating Systems
- f. Pressurizer Pressure and Level Control Systems
- g. Reactor Theory and Reactivity Balance
- 2. Simulator Training 5 Days Minimum
- a. First Session Orientation Plant Startup Plant Maneuvering in the Power Range Plant Shutdown
I COURSE SYLIABUS (Continued)
- b. Second Session Plant Startup Steam Line Break at Turbine Plant Transient
- c. Third Session -
F.'. ant Ac'cident E,jected CEA CVCS Rupture Recovery from a Reactor Trip
- d. Fourth Session Plant Maneuvering in the Power Range Plant Startup and Shutdown Reactor Startup Exercise Session
- e. Fifth Session Reactor Startup Exercis ssion Hot Leg Rupture Recovery from a Reactor Trip NOTE: This is a general format and specific lectures may be substituted to strengthen the program but the general intent must be adhered to.
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L"CTURE SERIES DURATION Course / Lecture Duration
- 1. Health Physics Unrestricted Course (3 days) 2h hours
- 2. Video Tape Lecture Serie's 135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />
- 3. Lecte aa A. Theory & Principles of Operation * (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> B. General & Specific Plant Operating Characteristics * (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C. Plant Instrumentation and Control (2 days) 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> D. Plant Protection Systems * (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> E. Engineered Safety Systems * (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> F. Normal & Emergency Operating Procedures * (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> G. Radiation Control and Safety (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> H. Technical Specifications * (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> I. Quality Assurance for Operations (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> J. Heat Transfer, Fluid Flow and Thermodynamics (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> K. Use of Installed Plant Systems to Control or Mitigate .
Accidents Involving Severe Core Damage (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> L. Reactor and Plant Transients * (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- 4. Walk-through Examination * (1 day) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 5 Written NRC Examination * (2 days) 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> l TOTAL 287 hours0.00332 days <br />0.0797 hours <br />4.74537e-4 weeks <br />1.092035e-4 months <br /> I
- Lectures to be given by individuals holding a Senior Operating License or proctored by c.n individual with a Senior Operating License.
I NOTE: Times are approximate depending on background of applicants.
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APPENDIX D LICENSED OPERATOR REQUALIFICATION PROGRAM
f OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 Licensed Operator Requalification Program A. PURPOSE
- 1. To ensure continued plant safety during all conditions of plant operations.
- 2. To improve overall plan't availability and operating efficiency.
- 3. To ensure continued licensed operator competence.
- 4. To demonstrate satisfactory compliance with federal regulations.
B. RESPONSIBILITY It is the responsibility of the Plant Manager through the Training Coordinator to ensure that the Requalification Program as described herein is administered.
C. APPLICABILITY Requalification training is required of all NRC licensed personnel
+ at the Fort Calhoun Station Unit No.1 to the extent indicated in the Requalification Program.
D. TERMINOLOGY
- 1. Quotation marks used in this requalification program indicate a quote from Appendix A of 10CFRSS, unless otherwise indicated.-
- 2. Those personnel holding NRC licenses at the Fort Calhoun Station Unit No.1 are hereby divided into two separate categories for purposes of this requalification program.
- a. Operating Staff - those licensed personnel who have been
" actively and extensively engaged as operators." At the Fort Calhoun Station Unit No. 1, this is synonymous with licensed personnel assigned to the shif t operating crew, i.e., Shift Supervisors, Reactor Operators and Assistant Reactor Operators.
- b. Staff Supervisors - those " individuals who maintain operator or senior operator licenses for the purpose of providing backup capability to the operating staff." At the Fort Calhoun Station Unit No.1, this is synonymous with licensed personnel not normally assigned to the shif t operating crew, i.e., Plant Manager, Operations Supervisor and other licensed personnel.
- 3. Accelerated Requalification Program (discussed in Section G) is a training program designated for those individuals (if any) who fail the annual written examinatien. These individuals will be removed from lir.ensed duties during the period of accelerated
D. TERMINOLOGY (continued) training. The scope and duration of the accelerated training will be dependent upon the individual's deficiencies.
- 4. Additional Train *ng Program (discussed in Section I) is a training program designated for those individuals (if any) who show unsatisfactory quiz, experience factor, or drill per-formance. These individuals will receive additional training to upgrade their performance in these areas.
E. SCOPE This program covers the methods to be employed to:
- 1. Schedule the requalfication program.
- 2. Administer pre-planned lectures.
- 3. Conduct on-the-job training.
- 4. Evaluate the performance of licensed operators.
- 5. Document the participation of each licensed operator in the requalification program.
F. SCHEDULE The requalification program will be conducted in two-year segments.
A typical two-year schedule is shown in Figure 1. The program will be conducted in a " continuous" manner; however, it will be tailored to traditional peak vacation periods and to planned plant outages.
G. LECTURES
- 1. Pre-planned lectures will be given to operating staff per-sonnel on the following topics in each two-year requalification program:
- a. Facility design changes, if any
- b. Procedure changes, if any
- c. Facility license changes (Technical Specifications changes), if any
- d. Operations Incidents and Licensee Event Reports (LER),
if any
- e. Emergency Procedures j
- f. Special lectures on major upccaing events such as re-fueling and major scheduled maintenance outages.
- g. Other lecture topics as deemed necessary by the Training I Coordinator from the list provided in Item 2 of this section.
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G. LECTURES (continued)
- 1. (continued) ,
Staff supervision personnel will not normally be required to attend these lectures because their normal duties require that they review the above topics. Documentation will be provided to insure that all licensed personnel have reviewed facility design changes, procedure changes, facility license changes, and abnormal and emergency operating procedures. Documentation will be in the form of PRC minutes and routing slips. These changes will be routed to licensed personnel in a timely manner. Abnormal and emergency procedures will be reviewed on a continuing basis by all licensed personnel.
- 2. All licensed individuals who fail the annual written examination (described in Section I) will be placed in an " accelerated requalification program." Licensed individuals that score low in particular categories of the annual written examination will be required to attend appropriate pre-planned lectures.
Lecture topies to be chosen for this program include:
- a. Theory and Principles of Operation
- b. General and Specific Plant Operating Characteristics
- c. Plant Instrumentation and Control Systems
- d. Plant Protection Systems
- e. Heat Transfer, Fluid Flow and Thermodynamics
- f. Use of Installed Plant Systems to Control or Mitigate Accidents Involving Severe Core Damage.
- g. Reactor and Plant Transients
- h. Engineered Safety Systems
- 1. Normal and Emergency Operating Procedures J. Radiation Control and Safety
- k. Technical Specifications
- 1. Quality Assurance for Operations
- 3. Approximately eight (8) months of lectures are covered by the pre-planned lectures as described in Item 1 above. Time allotted will be approximately fourteen (14) hours per man per month.
- 4. Evaluation of lecture series performance is dicussed in Section I.
- 5. Lecture series records are discussed in Section J.
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REQUALIFICATION PROGRAM SCHEDULE (TYPICAL) 2 YEARS A. Annual Written Examination M Lecture Series for all [
B. Operating Staff Personnel Accelerated Requalification ff
/
C. Program (if required) .
H/ '
On-the-Job Training CONTINUING IASIS D. (Drills)
On-the-Job Training CONTINUING BASIS E. (Experience Factors)
NOTES: (1) Item B is scheduled to take into account the peak vacation period (June 1 - September 1) and plant outages , such as for refueling.
(2) Item C will be scheduled on an individual basis for those who fail the written examination.
FIGUPE (1)
H. ON-TFE-JOB TRAINING
- 1. Every reasonable effort will be made to have each licensed operator perform a combination of control manipulations through at least ten (10) reactivity changes during any two-year requalification program to meet the requirements of -
10CFR55 Appendix A, Section 3a and 3b. If this is not pos-sible, a nuclear power plant simulator vill be used to insure compliance with 10CFR55 Appendix A, Sections he and 4d. If the simulator is used to meet the drill and experience facter portions of the requalification program requirements, the final evaluation of the actions taken or to be taken by the licensed individual vill be made at the Fort Calhoun Station control panels. In the event a simulator is required, the Combusi; ion Engineering pressurized water reactor simulator at Windsor, Connecticut will be used. The Combustion Engineering simulator reproduces the general operating characteristics of the Fort Calhoun Station Unit No. 1. The general arrangement of the instrumentation and controls of this simulator are similar to Fort Calhoun Station Unit No. 1.
If a simulator is used, approximately five days per man year of simulator time vill be provided.
The following control manipulations and plant evolutions are applicable to the plant design and are acceptable for meeting the reactivity control manipulations required by Appendix A, Paragraph 3.a. of 10CFR Part 55 The starred items belov vill be performed on an annual basis; all other items shall be per-formed on a two-year cycle. However, the requalification programs shall contain a commitment that each individual shall perferm or participate in a combination of reactivity control manipulations based on the availability of plant equipment and systems. Those control manipulations which are not performed au the plant may be performed on a simulator. The 'use of the Technical Specifications should be maximized during the simulator control manipulations. Personnel with senior licenses are credited with these activities if they direct or evaluate control manipulations as they are performed.
l *(a) Plant or reactor startups to include a range such that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established.
(b) Plant shutdown.
j *(c) Manual control of steam generators and/or feedvater during startup and shutdown l (d) Boration and/or dilution during power operation.
- (e) Any significant (. 10%) power changes in manual rod control or recirculation flow.
(f) N/A Any reactor power change of 10% or greater where load change is performed with load limit control or where flux, te=perature, or speed control is on manual (for HTGR).
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H. ON-THE-JOB TRAINING (continued)
- (g) Loss of coolant including: (1) significant FWR steam generator leaks; (2) inside and outside pri-mary containment; (3) large and small, including leak-rate determination; and (4) saturated Reactor Coolant response (PWR).
'+(h) Loss of instrument air (if simulated plant specific).
(i) Loss of electrical power (and/or degraded power sources).
- (j ) Loss of core coolant flow / natural circulation.
(k) Loss of condenser vacuum.
(1) N/A Loss of service water if required for safety.
(m) Loss of shutdown cooling.
(n) Loss of component cooling system or cooling to an individual component.
(o) Loss of normal feedwater or vormal feedwater system failure.
- (p) Loss of all feedwater (normal and emergency).
(q) Loss of protective system channel.
(r) Mispositioned control rod or rods (or rod drops).
(s) Inability to drive control reds.
(t) Conditions requiring use of emergency boration or standby liquid control system.
> (u) Fuel cladding f ailure or high activity in reactor coolant or offgas.
(v) Turbine or generator trip.
(w) bb1 function of automatic control system's) which affect reactivity.
(x) Malfunction of reactor coolant pressure / volume control system.
(y) Reactor trip.
(z) Main steam line break (inside or outside contain-ment).
(aa) Nuclear instrumentation failure (s).
+ Combustion Engineering simulator will not provide this function at present. Training on this manipulation will consist of classroom lectures.
- 2. Figure 2 (Experience Factor Record) provides for the documen-tation and evaluation of Reactivity Manipulations (as dis-cussed in Item 1) and other non-reactivity manipulations such as:
- a. Turbine generator startup
- b. Turbine generator shutdown
! c. Plant heat-up
( d. Plant cool-down l
- e. Liquid Waste Release l f. Caseous Waste Release l
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H. ON-THE-JOB TRAINING (continued)
- 2. g. Containment Entry
- h. Reactor Coolant Sample
- 1. Boron Analysis
- j. Contamination Survey
- k. Radiation Survey
- 1. Reactivity Balance Calculation
- m. Axial Flux Shaping
- n. Calorimetric Calculation
- o. Operation of auxiliary systems important to overall plant safety; i.e.rthose auxiliary systems specified in the Technical Spe'cifications. For example:
(1) Starting / stopping a RC pump (2) Establishing / terminating charging and letdown flow (3) Starting / stopping an auxiliary FW pump (4) Performing a surveillance test on the ENGINEERED SAFEGUARDS SYSTEH (5) Performing a surveillance test on the RPS The above list is not intended to be all-inclusive but only to be representative of the type of non-reactivity manipulation to be documented. There is no requirement on the number of non-reactivity manipulation experience factors to be performed in any two-year period.
- 3. Periodic drills (which simulate emergency conditions) will be given to each licensed operator. These drills will be accomp-lished on the control panel of the facility or by use of a simluator which meets the requirements of 10CFR55. Evaluation of these drills is discussed in Section I. Drill records are described in Section J.
I. EVALUATION
- 1. An annual written examination will be conducted which follows the format of the standard NRC written licensing examination.
Examinations will be tailored to emphasize those areas in which the licensed operator's prime responsibilities exist.
Failure on this examination (overall grade of less than 80%)
will require that the individual be placed on an " accelerated requalification program" as discussed in Section G of this program. Following the examination, a report will be issued
FIGUP.E 3 FORT CALHOUN STATION UNIT NO. 1 DRILL EVALUATION RECORD Na=e of EYAminee Name of Eraminer Date A. Description of Drill I= posed:
B. Drill Sy=ptoms given Ernminee: g D 3
$ ,-< Y a a a a 2 3 % %
C. Evaluation: N Y $1 E as v2 x m
- 1. Ability to quickly deter =ine type of abnor=al or emergency condition i= posed from given sy=ptoms.
- 2. Ability to respond correctly to abnor=al or emergency condition i= posed.
- 3. Ability to recover from abnor=al or -
emergency condition,
- k. Co=pliance with procedures.
5 Co=pliance with Technical Specifica-tions.
- 6. Ct-rall control of plant.
7 Knowledge of plant response without operator action.
Reviewed by:
Training Coordinator
- Required for grade of Excellent or Unsatis:factcry. -
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I. EVALUATION (continued)
- 1. (continued) summarizing weak topical areas and a list of those personnel, if any, who fail the examination. In addition, individuals who score less than 80% in particular category (ies) will be required to attend the appropriate lectures.
- 2. Periodic written quizzes will be given to all lecture studies participants to evaluate their knowledge on topics covered by these lectures. Failure on the quizzes is a grade of less than 80%.
- 3. Experience Factors (as discussed in Section H of this program) will most of ten be evaluated by Shif t Supervisors and periodically by licensed Staff Supervisors.
- 4. Drills (as discussed in Section H of this program) will be evaluated and documented on Figure 3 (Drill Evaluation Record).
Examiners (drill evaluators) will most often be Shift Super-visors and periodically licensed Staff Supervisors.
- 5. The evaluation of experience factors and drills will determine if the licensed operator "has demonstrated satisfactory under-standing of the operation of all apparatus and mechanisms and knows the operating procedures in each area for which he is licensed.
- 6. If unsatisfactory performance is indicated on Items 2, 3 and 4 above, the Training Coordinator will prescribe additional training as required. Up to fourteen (14) hours per man per month of additional training can be allotted to upgrade the individual's performance in these areas. The exact amount of time allotted will depend upon the nature and the extent of retraining required.
J. RECORDS
- 1. The following records will be maintained "to document each licensed operator's and senior operator's participation in the requalification program."
4
- a. The annual written examination along with the graded answer sheets,
- b. Lecture series attendance and a copy of each quiz ad-ministered and the graded answer sheets.
- c. Completed copies of Figure 2 (Experience Factor Record) so that the satisfactory performance of ten reactivity manipulations in a two-year requalfication program can be demonstrated.
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J. RECORDS (continued)
- 1. (continued)
- d. Completed copies of Figure 3 (Drill Evaluation Record) to demonstrate performance of simulated emergency or abnormal operations.
- e. Participation (if required) in an accelerated requali-fication program or in an additional training program.
- 2. The records described above will be maintained as required by the Fort Calhoun Station Technical Specifications.
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