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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
...
Omaha Public Power District 1623 HARNEY a OMAHA, NEBRASMA 68102 e TELEPHONE S36 4000 ARE A CODE 402 August 19, 1982 LIC-82-298 Mr. Robert A. Clark, Chief U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C. 20555
Reference:
Docket No. 50-285
Dear Mr. Clark:
NUREG-0737, Item II.K.3.17 Report on Outages of Emergency Core Cooling Systems (ECCS)
The Commission's letter to Omaha Public Power District, dated July 14, 1982, requested the District provide additional information regarding the subject TMI Action Plan item. Accordingly, the attached Tables 1, 2, and 3 provide the information requested by Item 1 of the subject letter and the attached Table 4 provides the information requested by Item 2.
Table 1 specitically identifies diesel generator outages resulting from surveillance testing activities. Tables 2 and 3 detail diesel generator outages resulting from component failures identified by planned, un-planned, or preventive maintenance. Table 2 includes all planned and preventive maintenance outages and Table 3 identifies the unplanned maintenance outages which were reportable as Licensee Event Reports.
Table 4 addresses all ECCS component outages resulting from surveillance testing.
In most cases, the exact duratir,n of a specific surveillar. e test was not available, so a best estimate, based en the average aui ation of completing the test, has been provided. It shoulo 31sc be noted that removing a component from service for surveillance testing does not necessarily render that specific ECC train or system inoperable. As an example, Surveillance Test ST-SI/CS-1 (listed in Table 4) requires the 00 8208240(7%
?
Mr. Robert A. Clark .
LIC-82-298 Page Two operability testing of all safety injection and containment spray pumps, one pump at a time. Although one pump is removed from service for testing, the additional redundant pumps permit the system and its trains to remain fully operational.
Sincer ly, l$ wp W. C. nes Division Manager Produ'c' tion Operations WCJ/TLP:jmm Attachments cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C. 20036 l
l 1
l 1
l l
F'
,. .i TABLE 1: DIESEL GENERATOR OUTAGES FOR SURVEILLANCE TESTING Surveillance Test, Section Frequency Date Duration
- Component (s) Remarks ST-DG-2; F.1, Annual 3/12/76 84 hr. DGl During Cold Shutdown F.2, F.3 3/14/76 Diesel Gen. 1 Inspection and 2/26/77 Overhaul 2/10/78 2/13/78 2/13/79 2/16/79 11/16/79 11/11/80 V V 11/13/80 'I V ST-DG-2; F.4,F.5, Annual 3/1/76 84 hr. DG2 During Cold Shutdown F.6, Diesel Gen.
20 Inspection and 4/20/77 Overhaul 3/16/78 3/20/78 5/4/79 2/15/80 v V 2/18/80
'I V ST-ESF-2,4,13;F.1 Monthly 1/22/76 4 hr. DG1 h el fg lnjec. 2/26/76 0 Not Performed-Cold Shut.
Actuation, 3/23/76 4 hr.
Containment Spray Actuat.1on 4/22/76 and Recircula- 5/20/76 tion Actuation Signal Tests 6/24/76 7/22/76 8/26/76 9/23/76 V 10/21/76 0 Not Performed-Cold Shut.
y V 11/8/76 0 V Not Performed-Cold Shut.
o This is an estimate of the average time spent performing this test. The actual time spent for each test is unavailable.
1-1
TABLE 1: DIESEL GENERATOR OUTAGES FOR SURVEILLANCE TESTING (Continued)
Surveillance Test, Section Frequency Date Duration
- Component (s) Remarks ST-ESF-2,4,13;F.1 Monthly 12/22/76 4 hr. DGl 1/11/77 Performed to verify operability of safety-related equipment in containment after in-advertent introduction 2/28/77 of water into contain-ment spray rings during 3/25/77 routine surveillance of containment spray 4/21/77 pumps.
5/26/77 6/23/77 7/21/77 8/25/77 9/22/77 10/29/77 0 Not Performed-Cold Shut.
11/25/77 0 Not Performed-Cold Shut.
12/22/77 4 tr.
1/26/78 2/23/78 Y 3/23/78 # Gage was not qualified-3 (
Calibrated gage-Retest on 3/28 ST-ESF-2; F.1 -
3/28/78 2 hr. Retest of ST-ESF-2, F.1 only ST-ESF-2,4,13; Monthly 4/20/78 4 hr.
F.1 5/25/78 6/22/78 7/20/78 8/24/78 y 'l 9/21/78 Y Y o This is an estimate of the average time spent performing this test. The actual time spent for each test is unavailable.
1-2
TABLE 1: DIESEL GENERATOR OUTAGES FOR SURVEILLANCE TESTING (Continued)
Surveillance Test, Section Frequency Date Duration
- Component (s) Remarks ST-ESF-2,4,13;F.1 Monthly 10/78 0 DG1 Not Performed-Refueling Outage 11/23/78 0 Not Perfonned-Refueling Outage
- 2/22/78 4 hr. Performed prior to start-up from refueling outage 1/25/79 2/22/79 3/21/79 4/24/79 5/25/79 6/22/79 7/26/79 8/24/79 9/20/79 10/25/79 11/21/79 12/21/79 I 1/24/80 0 Not Performed-Refueling Outage 2/21/80 Not Performed-Refueling Outage 1
3/20/80 Not Performed-Refueling Outage l 4/24/80 Not Performed-Refueling Outage 5/22/80 V Not Performed-Refueling Outage 6/26/80 4 hr.
7/24/80 8/21/80 V y 9/24/80 w '
I o This is an estimate of the average time spent performing this test. The actual time spent for each test is unavailable.
1-3
l TABLE 1: DIESEL GENERATOR OUTAGES FOR SURVEILLANCE TESTING (Continued)
Surveillance Test, Section Frequency Date Duration
- Component (s) Remarks ST-ESF-2,4,13; Monthly 10/23/80 4 hr DG1 F.1 '
11/20/80 3, 12/26/80 V V ST-ESF-2,4,13;F.2 Monthly 1/8/76 4 hr. DG2 Channel B Safety Injec-2/13/76 h tion Actuation, 3/11/76 1 hr. ST-ESF-4; F.2 only Contain. Spray perfonned during Actuation, and cold shutdown fa n g. 3/23/76 3 hr. ST-ESF-2,13; F.2 Tests performed prior to start-up 4/8/76 4 hr.
- 5/6/76 6/10/76 7/9/76 ST-ESF-2,13, F.2 only 8/12/76 9/9/76 I
I 10/7/76 0 Not Performed-Cold Shut.
11/8/76 0 Not Performed-Cold Shut.
12/8/76 4 hr. Performed prior to Start-up from Refueling Outage 1/20/77 2/11/77 3/10/77 4/7/77 5/12/77 6/10/77
'( 8f 7/7/77 ' ( V o This is an estimate of the average time spent performing this test. The actual time spent for each test is unavailable.
1-4
m TABLE 1: DIESEL GENERATOR OUTAGES FOR j SURVEILLANCE TESTING (Continued)
Surveillance Test, Section Frequency Date Duration
- Component (s) Remarks ST-E S F-2,4,13 ; F.2 Monthly 8/11/77 4 hr DG2 i
9/8/77 10/29/77 0 Not Performed-Refueling Outage 11/25/77 0 Not Performed-Refueling Outage 12/12/77 4 hr.
1/12/78 2/9/78 3/9/78 4/5/78 5/11/78 6/8/78
, 7/10/78 i 8/10/78 9/7/78 l
10/12/78 [
- 11/9/78 0 Not Performed-Refueling I Outage 12/14/78 0 Not Performed-Refueling Outage 1/11/79 4 hr.
2/8-9/79 24 hr. Selector switch failed (M0 #21751). Test com-pleted after M0 on 2/9/79 3/14/79 4 hr. HCV-311 did not open.
Rechecked 4/19/79 5/4/79 l
6/7/79 l
'l '
I 7/6/79 I V
- This is an estimate of the average time spent performing this test. The actual time spent for each test is unavailable.
l-5 l
t
i l
TABLE 1: DIESEL GENERATOR OUTAGES FOR SURVEILLANCE TESTING (Continued)
Surveillance Test, Section Frequency Date Duration
- Component (s) Remarks ST-ESF-2,4,13;F.2 Monthly 8/13/79 4 hr DG2 9/6/79 10/11/79-11/8/79 12/7/79 :
1/10/80 3 (
2/7/80 0 Not Performed-Refueling Outage 3/6/80 0 Not Performed-Refueling Outage 4/10/80 0 Not Performed-Refueling Outage 5/8/80 0 Not Performed-Refueling Outage 6/12/80 4 hr.-
7/10/80 8/7/80 9/11/80 10/9/80 11/5/80 i
i 12/12/80
( V O This is an estimate of the average time spent performing this test. The actual time spent for each test is unavailable.
i.
. 1-6
Enclosure ! -
TAbil. 2 p
Plant !!sme fort Calhoun Diesel Generator Scheduled Downtime Record Unit flo. 1 ,.-
Calendar Year 19,_76 Ilours of flount ime Outage Date neactor shutdown Reactor not shutdown Reason for Outage n y-
- Ug r'- Ug r T c r T F li{F { ogf oc# oci 2/23/76 3d ,2il Overhaul SM 3/10/76 190.5H _ Service & Inspection per MP-DG-1 (overhaul) 3/18/76 12.lH Connected 20003 Res. across contacts 3 & 4 of CR-120 relay.
4/27/76 1.6 D-2 Pri. Air St. Motor Didn't Disengage 5/13/76 1.0 k!plS$$i3iONc!!"kuelline 5/17/76 3411, . Change Lube Oil & Filters Per EM Manual 34M 5/26/76 7 11 ,
Check coupling alignment on soak back filter 14M (Lovejoy coupling spacer replaced) , .
6/7/76 SM No additional information available 8/15/76 22H, Adjust Speed Switch 30M Pres. Switch for Secondary Air Not Working 8/16/76 _57M Also Solenoid Valve Leaks 9/27/76 .
No additional information available 10/20/76 12d, 1 111, Overhaul 15M 11/9/26 ,
Calibrate DG-2 Metering
,W'
/
m - . -
Enclosure ! -
- Taut.E 2 Plant flame Fort Calhoun Diesel Cencrator Scheduled Downtime Record 1
Unit lio. l ..
Calendar Year 19_77 liniers of Downt ime Outage neactor shistdown neactor not stiutdown Reason for Outage Date ~Dcr 7gP-- Ugr TiCF 7iCF- in:t
'ligT- prji nc# nct Speed switch improperly set - striking 2/1/77 7H, flywheel 25M ,
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2/22/77 94H Overhaul 4/11/77 70H, Overhaul- Check pitch of fan blades 48M 4/18/77 54H, Remove, clean and inspect secondary air 42M system 5/23/77 27H, Change engine coolant, DG-2 8/26/77 lH, Check and repair leaks on lube oil 18M expansion tank 10/12/77 7H, No additional information available 45M 10/26f77 7H No additional information available 12/9/77 lH Repaired transducer for ampmeter.
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TAl!:J. 2 Plant flame Fort Calhoun Dicael cenerator Scheiluleil Downtime Record Unit lio. 1 ,.
Ca".cnilar fear 1919 llours of Downtime Outaae neactor shutdown neactor not shotanwn eason for Outage Date ~UyT-~ 7 ]I-~~DgT' UUF uca ]T- gl~'- Igl Dcl Dcl Remove Thermostatic Valves from Jacket 2/12/79 105H Water TCV, check for proper travel 0 rated temp. Annual overhaul.
3/9/79 __ lit , DG-1 fails to start, relays 104 Elx and ~
15M 104 E2X chatter and arc Lube oil recirc. pump - faulty 4/4/79 lH, coupling 30M 4/23/79 37H FCVS Removed, calibrated, replaced 4/30/79 12711.
15M Overhaul 6/28/79 7H Maintenance to 1AD1 breaker.
11/12/79 133H TCV's for DG-1 cal. and/or replaced.
Annual overhaul.
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ed as
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Enclosure ! -
TAnl.E 2 Plant usme Fort Calhoun
- Dicael Cencrator Sclieduled nowntime Record 3 Unit tio. ..
Calendar Year 1980 Ilours of Downtime Outage
. Date cact or stintdown Reactor not sim t duun .
Reason for Outage
'DGI~ ~~DgT ~Dyl~ ~n:rmiCY }T~ f ny:1~ oci uct Diesel DI Immersion heated control trans-7/9/80 SH former failed due to unknown causes. Re-placed with GE transformer.
7/16/80 __ 27H, Replaced rusted out portion of exhaust 18M pipe on DG #1 ,
8/11/80 4H, Changing lube oil. ~
50M 8/13/80 33H, Changing lube oil.
6M Immersion heater DG-1 needed replacing.
9/10/80 8H Replaced trans. T-4.
224 ,
9/24/80 10H, Repair lube oil leak.
23M 9/25/80 '
27H, Repair lube oil leak.
45M 9/29/80 10H' DG-1; Various alarms on the lube oil and cooling water. Checked circuits - recon-31M nected wires.
10/27/80 1H, Replaced Immersion Heater Contactor on DG-1.
48M Damaged by Transformer failure on 7/9/80 11/5/80 3H DG-1 failed to start upon actuation of chan-nel full speed test switch. All circuitr 4$f.-
including wire connections were ch'ecked yOK 11/10/80 88H
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30s Overhaul 11/14/80 2H*
Broken air line from air start solenoid on DG-1. Replaced broken air line.
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I8N DG-1 failed to start on secondary air start 12/11/80 A4 motors. Cleaned air start motors.
24M w -e
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Enclosure I
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TADI.I. 3 111coc1 Cenerntor Ifonctieduled Ilountime Record l'I n n t finne Fort Calhoun .
Calendar Year 1976, 80 ~
Unit Ito. 1, N,
nun uto - 11 any I tiie regi r ed f allmes would not leave been a 1.En Alis t rac t 11. . Downt ime flours fn!!ure under emergency conditions, plenoc cuplain lierc.
(Itcle r t o at tcl " " ~
E! '*I*' E "EE**I'*d I" "' "# EI'* I*II"'*' II'E' I" I#I'I" I*
ed I.En AI,stract "'I'" r s)Ilours alioo t t eig tvern etc tcplace s.
76-16 <24 s4 78-22. <24 heeAttachedLERs S -
78-24 <24
)
80-14 5 80-30 ,
<24 1
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TABLE 4: ECCS COMPONENT OUTAGE FOR SURVEILLANCE TESTING b
Surveillance ~
Test, Section Frequency Date Duration
- Component (s) Remarks ST-SI/CS-1, F.1 Quarterly 1/13/76 4 hr. LCV-383-1/2 Functional HCV-383-3/4 Testing of 4/14/76 Some high and low SI-1A/lB readings in alert Safety Injec. SI-2A/28/ range. Retest on and Contain. 2C - SI-3A/
Spray Pumps 3B/3C 4/15 and Valves 4/15/76 Retest gave satis-factory results 10/14/76 0 Not Performed-Refueling Outage 1/12/77 4 hr. HPSI SI-2A discharge valve did not open with control room switch.
Operator opened manually (repaired under M0 #13265).
3/24/77 4 hr. Test run to check oper-ability of Containment Spray Pue.9s to satisfy interim Tech. Spec. 6.6 4/12/77 4 hr.
7/13/77 s/
10/77 0 Not Performed-Refueling Outage l 1/78 4 hr.
4/12/78 7/12/78 V 10/78 0 Not Performed-Refueling
- Outage 1/17/79 4 hr.
4/20/79 y 7/26/79 3 r
9 V
o This is an estimate of the average time spent performing this test. The actual time spent for each test is unavailable.
I 2-1
0-TABLE 4: ECCS COMPONENT OUTAGE FOR SURVEILLANCE TESTING (Continued)
Surveillance Test, Section Frequency Date Duration
- Component (s) Remarks ST-SI/CS-1, F.1 Monthly 9/11/79 4 hr. LCV-383-1/2 HCV-383-3/4 10/16/79 SI-1A/1B
-2A 11/19/79 LCV-383-l has a packing A/ leak. HCV-2908 won't 3B/3C close (M0 #2804).
12/15/79 1/18/80 d 2/12/80 0 Not Performed-Refueling Outage 3/11/80 Not Performed-Refueling Outage 4/15/80 Not Performed-Refueling Outage 5/13/80 $( Not Perfonned-Refueling Outage 6/17/80 3 hr. SI-2B not tested due to MO on HCV-2908. SI-2B tested satisfactorily on 8/12/80.
! y 7/15/80 4 hr. HCV-2908 would' not close (M0 #6231) l -
8/11/80 1 hr. Retest of SI-3C only i from 7/15/80
( Monthly 8/12/80 4 hr.
I 9/16/80 3 hr. SI-2C was not tested because HCV-2918 would not close (M0 # 7687) y y 10/14/80 4 hr. y SI-1B vibration in alert.
l oThis is an estimate of the average time spent performing this test. The actual time spent for each test is unavailable.
i 2-2 L-_, . - . - - - .
TABLE 4: ECCS COMPONENT OUTAGE FOR SURVEILLANCE TESTING (Continued)
Surveillance Test, Section Frequency Date Duration
- Component (s) Remarks ST-SI/CS-1, F.1 -
10/28/80 1 hr. LCV-333-1/2 SI-1B retested. Still HCV-383-3/4 in alert range.
Monthly 11/8/80 4 hr. SI-1A/lB 11/18/80 4 hr.
Sf-2A28 p Excessive vibration.
required action range 3B/3C 3
r -
11/21/80 1 hr. 4 Realigned bearing. Re-tested pump o This is an estimate of the average time. spent performing this test. The actual time spent for each test is unavailable.
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F LICENSEE EVEffT REPORTS l
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LICENSEE EVENT REPORT 50-285/76-16 COffTnOL ULOCK:l l l l l l l (ptrAUC PntNT ALL DCTUIRED INFoHMATION 1 U tctNStf NAM ( tctNst EviNT LCENSE NUMBER TYPE TYPE l nlE lF l Cl Sl ll l0 l0 l-l 0 l 0 l 0l 0l 0l-l0 l 0 l l 4 l 1 l1 l1l1l [0[3]
UD 14 lb 2b 2G 30 31 32 cAf tC04Y Tv$ sYu N OOCKET NuMotn Ecen lb7 7 0 1
50 l Ltd 59 IL_J GO 101510 I-10 l e i 81 si tytNT OATg l0lh121717l61 10 is 11 il 17 i 6 ntPOnT DATE G1 68 09 74 7b UC EVENT DESCRIPTION a? lAt 1616 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.14888e-4 months <br /> on April 27, 1976', the primary air start motor for DG-2 failed to dis-7 89 l o Oc l engage after DG-2 was successfully started and at 100 RPM. The redundant diesel 7 H9 l 00 04 l generator, DG-1, was started and run to prove operability; both redundant offsite 7 Uu l
@ l power sources, the 161 KV and the 345 KV vere also operable. (LER 50-285/76-16) 7 H9 l bl 7 U9 l
,,.M r tysit u CAUSE rmurONENT 80 CODE CODE COMPONE NT COMPONENT CODE SUF'PLE R
@ lElEl W M ANUFACT UFE R VOLATION 7 00 10 11 l I l N l Sl Tl Rl u l 12 17 W43 l XJ 9l 9l 9l 44 47
[N j 40_
CAUSE DESCO PTION
@ l The airgan setting for the magnetic pickup unit for the airpax electronics switching l h l tachemeter was not set correctly. 80 7 09 l 1O l f *Ca riv METHOD OF
]
LIAIUS % POWEA OTHin ST ATUS Q
OtGCOVERY OiSCOVERY OESCA:PTON l0l9l~8l
[E_J l, NA l (Bj l Maintenance Test 7 8 9 10 12 13 44 45_
l 46 80 ACT fVTT Y COdifNT HELEASED OF ACLE ASE 2a LOCATON OF RELEhSE 7 U 9 LzJ LzJ 10 11 l n^ AMOUNT OF ACINITY 44 l I "^ l 4S PERSONNEL EXPOSURES 80 NUMOI A TYPE DESCA4PTON
$ 1010101 7 89 L zJ l n^
l 11 12 13 60 PERSONNEL INJURrES NUMDf R DE SCRIPTON i 14 l0 l0 l 0l l NA 1 09 11 12 l 80 OrrSITE CONSEQUENCES '
l 1 00 l n^ l LOSS OR OAMAGE TO FACILITY 00 TYPE Ot SCHIP T ON *
, IIBINA l U9 00 l ADO:TIONAL FACTORS *
] l See Attachments 1, 2 and 3 U9 l 00
- TE I 09 l Uo NAME
- - John M. Nagl '
h02 h26 h011 PHONr. j
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V Licensee Event Report 50-285/76-16
. Page Two-
. Attachment No. 1 t
i Cafety Analysis Even though DG-2 did properly start at 1616 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.14888e-4 months <br /> on April 27, 1976, it was administratively deemed inoperable since the primary air start motor failed to disengage at 100 rpm. At 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br /> DG-1 was started and run to demonstrate operability. While DG-2 was inoperable off-site 161 KV power was operable and supplying engineered safeguards buses 1A3 and 1A4 with off-site 345 KV power available to buses 1A3 and 1A4 should the 161 KV supply fail. In addition, DG-1 would have supplied bus 1A3 (DG-2 feeds bus 1A4) had all off-site power been lost. There were no inoperable engineered safe-i guards components associated with bus lA3 while DG-2 was inoperable. All requirements of technical specification 2.7.(2)i vere satisfied, plant safety was not , jeopardized and no limiting condition for operation was violated with DG-2 inoperable.
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1 Licensee Event Report 50-285/76-16
Attachment No. 2 l
Corrective Action The magnetic sensing unit for the switching tachometer (speed switch) had been removed on April 27, 1976, so that routine maintenance could be per-formed on DG-2 air start motors. This sensing unit is in close proximity to the air start motors and interferes with accessability for air start motor maintenance. After completing maintenance on the air start motors, DG-2 was started to prove operability. This start was called for by pro-cedure. After sensing 100 rpm the speed switch generates a permissive signal to disengage the air start motors. However, due to the improper air gap setting, the speed switch failed to generate this permissive and the air start motors consequently did not disengage. The air gap for the magnetic pick up unit was properly set and DG-2 successfully started with proper disengagement of the air start motors at 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br /> on April 27, 1976 (see Maintenance Order No. 10918). The error was procedural in that the maintenance proccoure did not call for checking the air gap setting whenever the speed sensing unit is re-installed. Hereafter this setting vill be checked.
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- - Licencee Event Report 50-255/76--16 l
. Attachment No. 3 ,
t Failure Data-i
! This is the first occurrence of an improper air gap setting for the
- speed sensing unit for a diesel generator at the Fort Calhoun Station Unit No. 1.
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ILICENSEE EVENT REPORT CONVROL BLOCd: l l i
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lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI T l3 l9 U l zLICENSEEl P lCODE c I s l l l@150 lo 10 lLICENSE 14 0 lo NUM8EH l01010 l0101025 l@l4 26 l1 l1 13 l, l@l57 CAT LICENSE TYPE Jo l
$8 lg WT E $
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60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE do EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h g lDuring the monthly load test of diesel generator number 1 the generator field vent to 1 7 q ; maximum excitation and was shutdown to prevent generator damage. Three problem areas l p l vere discovered: the field boost relay had drifted, the reference P.T. stab was looseI
- ., ) gand the regulator reference zener was found defective. The items were repaired and I g j lthe diesel retested and returned to service. I
~iT) l I 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUSCODE COMPONENT CODE SUSCODE SUSCODE y
s lE lE l@ Q@ J@ l Gl El Nl El Rl Al@ W@ y @
9 10 18 12 13 18 19 20
_ SEQUE NTI AL OCCURRENCE REPORT REVISION LE R RO EVENT YEAR REPORT rJO. CODE TYPE N O.
t a7
@ suNE _ 21 l 7l 8l 22 l-l 23 l 0l 2l 2l 24 28 y l0 l3 l l Ll l-l lo l 27 28 29 30 31 J2 Ta N ACT ON ON PL NT MET HOURS S8 1T FOR 8. SUPPLIE MANUFACT RER lA JJ j@lJe Zl@ lZ l@
35 U@
36 l0l0l0l0l 37 40 W@ lUl@ lAl@
41 42 43 l G l 0 l 8 l 047 l@
44 CAUSE CESCRIPTION AND CORRECTIVE ACTIONS j , ; lThe field boost relay was found to have drifted, the reference P.T. stabs vere leese I
- , j land the reference tener diode for the generator regulator was found defactive. % I
,,, gite=s were repaired. This is the first failure of this tyne and no further action is 1 y l anticipated. The tener diode was felt to be the failure mechanism. I TTl l I s > . 80
' STA
- C TS sPOwER OTHER STATUS h ESEOSRY DISCOVERY DESCRIPTION y [E l@ l 0 l 9 l 8 l@l NA l lBl@l Surveillance Test l Ai'miTY CaTENT RELE ASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELE ASE NA l l NA l le s13 1: l @ LEJ@l to 11 44 45 80 I
PERSONNEL EXPOSURES t
NUV8ER TYPE DESCRIPTION j id 1010 lo l@[lj@l NA ,
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,ERSONNELINJJiES l
NUM8ER DESCRIPTION N
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_LJ d 3 lo l o l0 l@l1211 80 l
l LOSS OF OR DAMAGE TO FACILITY i
TvPE DESCRIPTION l NA l I 31 l9l 2 l@l10 80
'UBLICITY NRC USE ONLY *
.SSt E DnDESCRIPTION .
y WQ4)l NA ,1 M. l Illl!lIIlllll1 4 J 10 h 68 69 80 &
[ y,g g , R. Mehaffey/G. Peterson' pm h02 h26 h011
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- i LER 78-022 Cmaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 Attachment No.1 Safety Analysis i
2 The Fort Calhoun Station electrical distribution system is so designed that no single failure can prevent the safe shutdown cf the plant if required. During the time that diesel generator number 1 was inoperable, diesel generator number 2, the 161 K7 supply, and the 345 KV supply were available.
The initial failure (generator overexcitation) occurred on July 12, 1978.
At this time an investigation was initiated in an attempt to discover the failure
=echanism. The investigation showed that the current boost which actuated on low generator tenminal voltage had drifted up. This drift upward coupled with a low grid voltage due to summer load on the 161 KV grid was felt to be the failure
~
=echanism, since the generator goes to maximum excitation on actuation of the relay. The relay was reset and the diesel was load and run for approximately 1
20 minutes on July 13,1978 (this short load time was due to an electrical storm at the station which could potentially damage the diesel while synchrcnized to the bus). The diesel was considered operable at this time.
On July 14, 1978, the monthly surveillance test was repeated on diesel generator number 1 to completely verify operability. At approximately 55
=inutes into the test the generator again went to maximum excitation and was subsequently tripped. Upon further investigation, two problem areas were identified. The generator terminal reference potential transformer plug in stabs were found to be loose, which may have caused the overexcitation, and the reference voltage sener diode in the generator voltage regulator was found to be defective, which could have caused the failure. The stabs were repaired
, and the ener was replaced with a 10W 2hV sener diode (the original equipment
] zener diode is no longer available). General Electric was consulted on the
! change to an ECG5198 diode and concurred with the replacement diode. The voltage stability of the generator was then reset and recovery time was tested snd set at less than 1 second at no load. Per telecon with General Electric l on July 1h,1978, the worst case recovery is at no load.
The diesel was then retested and found to be operable on July lh, 1978, by surveillance test ST-ESF-6. This is considered to be an isolated failure and no further action is anticipated.
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4 IIR 78-022 Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 05000285 Attachment No. 2 Failure Data This is the first failure of this type at the Fort Calhoun Station Unit No.1.
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CCNTACL SLOCK: l l l l l I lh (PLEASE PMINT OA TYPE ALL AEOUIRED INFCRMATION) g li g
- l rLiCEN5EE i r i cC00Ei s li l@l o lo lo loLiCEN5E 14 15 lo loNUM!$ER lo 10 lo lo lo l@l LILICENSE 25 26 il 11TYPE il JO il@l57 GAT i 3d l@
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{ d 3cS#]60l L !@l 61 0 l 5 COCKl 0 ETl 0NUMB l 0E Rl 218 ba15 l@l 69 0EVENT l 8 10 DATE l9 l 7 72l8 I@l0 75 l9 l0 11 l7 la40 l@
REPORT O ATE EVENT DESCA1PTION AND PACS A9LE CONSECUENCES h g lOuring the Onthly load test of Diesel Generater No.1 the field vent to =axi== exci_ :
g ;tatien and was shut devn to prevent generator damage. The failure was a result cf ll l
- ,greference
- ener diode drift and probable bus conditions ccupied with a pcsitiva 'aad- li g ;back drcep c =pensatice. "he diode vas replaced and the generator current restricted l T"i-] l for 1
- ad tests when paralleled to the bus. The generater was retested successfully. I l I'l 1 l IIJ l I 4 9 _ _-
- do SYSTEV ... CAUSE CAUSE Coup. vatvE COCE CODE SUSCCOE COM*0NENT OCOE sug OCE $U5000E E d 9 I ? !r l@ llj@ l cl@ I c I2i v i n i r l a l A l@ lx i@ l ZI @
10 ft 12 18 19 20 SEQUENTI AL CCCUR A ENCE REPORT AEVISICN
,_EVENTYEAR R EPORT NO. CCOE TYPE N O.
@ ; lea e;g;a0 I7Iei 21 1-1 23 I oI al hl 24 1/l _I n I , I [.,7_J I-1 [ 2_l 22 26 27 '8 29 30 31 ;2 A C? t C N #UTURE EFFECT SHUTCCwN ATT AC M*> E N T N'R D-4 PRIME COMP. CCMPONENT Ta%2N a:TICN CN PLANT METHOD wCURS SUB uiTTE D FORusus. SUP* LIER M AN UF A CTU R E 4 IA !@l Zi@ l Z l@ l36 Zl@ l 010101 o f I Y l@ INI@ lal@ l o l o l
J; ;4 35 33 40 41 42 43 da 47 CAUSE CESC AIPTICN AND CC A AECTIVE ACTIONS i a l lThe d-ift of the reference :ener dicde and generator characteristics when paralleled tel g [the bus was the failure mechanism. The :ener was replaced a-d ad-4"4strative li=its en !
,,; parallel bus operation were imposed. "his is the second related failure. No fiu ther i g l action is anticipated. _ l l i.), ,
a 9 30 FaC:uiv METHOD 08 STa?.s *,70nEA OTH ER STA TUS CISCOVE A V DISCOVERY DESCRl*TICN 9 irl@ lo!oIel@l d 9 to 12 11 MA 44 l lBl@l 45 46 Su vein ance test 80 l
AC TIVI TY CON T E NT 2ELEASED OraELEASE AMOUNT OF ACTIVITY LOCATION 05 AELEASE 9 aI Jz l @ l cl@l NA 10 is 44 I I e5 NA 30 I
- E45CNNEL ExPCSVAE5 Nuv8fA TV'E C E 5CRisTION 9 3I o 3 I o Io !@lZ l@l NA 11 T2 13 i
SO 8 E A SCNN E L 'N;i.,a E5 NuvSE4 DESC2iptsON 3 3 lC l c 10 lh 12ITA 11 30 I
LO53 C8 CA DavaCE TO pactLITV
%8E OtscaisitON l3 NA
<> 0 u 8V8LICITV N AC USE ONLY 55UEa OtsCRiPTION
} l3 l -Q n ,[ ! ll ll l !!Il l l 1I g 3 0 , f, 48 69 30 NAveos mE=AAsa R. Mehaf ey/G. Petersen pycyg WM-C
j' LIR 73 s02k Cnaha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 05000285 ATTACEENT NO.1 Safety Analysis The Fort Calhoun Station Unit No. 1 Engineered Safety Features Systa=
is so designed that no single failure can prevent the safe shutdown of the plant if required. During the ti=e Diesel Generator No. I was inoperable (during repair and testing), Diesel Generator No. 2 was operable and both the 161 K7 and 3k5 KV supplies were available.
During the period of trouble shooting and testing on August 9,1978, with the exciter =anufacturer and subsequent testing on' August 30,.1c78, as recc== ended by the exciter manufacturer, the following infor:stion was discovered: .
(1) During the initial one hour run which lead to the failure of Diesel Generator No.1, it was noted the _ generator cut-put current centinued to increase throughout the entire run vithout any operator action.
(2) A bench test of the reference ener diode shoved continual drift up. This was the tener which was replaced and reported in LER 78-022. The drift was within =anufacturer tolerance. The original diode was ther= ally ec=pensated and exhibited a smaller drift, hcvever, this exact replace-
=ent is no longer =anufactured.
(3) At the time the failure occurred, the generator exciter was approx *-ately at its naxi=u= long time exitation limit, which was approaching the saturation limits of the machine.
(h) The generator droXp cc=pensation is vired to boost current if generator current increases, rather than a nor=al machine set up for parallel operation on a bus, in which the droop ccmpensation tends to limit current.
Eased on the data and information collected during testing and trouble-shcoting Diesel Generator No. 1, the following hardware and procedure changes vere instituted:
(1) The :ener diode referenced earlier was changed ou: to a 5CW
- ener diode to provide greater stability. The subsequent test shoved the diode did drift but to a =uch s=a er extent than the 10W :ener.
(2) The generator exciter circuit was designed to provide maxi-
-"- -"---
- boost in starting the Ingineered Safety Features Leads. As a result of this, when paralleled to the bus , the
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. E LER TS-02h -
C=aha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 05000285 ATTAC*
r E T NO. 1 (continued) drcop CT influence on the regulator operation may not be able to be ec=pensated for by a change in ter=inal voltage on the =achine (parallel operation vill result in small terminal voltage changes with excitation and large current changes or power facter changes). To li=it current output of the generator,ad=inistrative centrols have been placed on the machine during parallel operation to li=it the current to belov 400 a=ps at 2500 l KW (which is away frc= the saturation region of the nachine). A cc=puter alar = for the generator has also been provided to alar = at h00 a=ps.
l In discussing this proble= with the exciter =anufacturer and based on the test data.it has been deter =ined than though the generator failed when paralleled to the bus, at no ti=e was it inoperable, if required, to perfc== its design function for Engineered Safety Feature creration.
When the generater is operated carrying the ES? loads, after the initial lead starting, it vill provide only the current required to =aintain the lead. Any shift of the exciter circuit vill result in a drift of ter-
=inal voltage and a small drift (aV/Z) of ' current, negating the droop cc=pensatica effect.
l The failure during parallel operation was deter =ined to result frc=
- two areas; the drift of the ener diode and a s=all load change on the bus during the generater test. The ener diode drift and bus condition resulted in the generator being at approximately the =axi=un long time excitation li=its. Any s=all voltage decrease or lead increase On-the l bus at this time vould have required more current out of the generator, l
resulting in the drcop circuit positive feedback, increasing excitation with little er no negative feedback frc= the exciter's voltage input.
At this time the machine vent to maxi =u= excitation and blev the field protection fuses.
The generator was subsequently retested and the current was 1L=ited belev h00 a=ps. No proble=s were encountered and no further action is anticipated.
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) LIa 78;02h C=aha Public Power District Fort Calhoun Station Unit No. 1 Oceke :To. 05000265 A"'TACBE:IT !!O. 2 Fail e e Data A previcus failure was reported on LER 78-022. -
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. LICENSEE EVENT REPORT /
CONTROL BLOCK. l
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l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) f f) Y'b" ' t' )
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I ELl;tNSEE l F ! CCODEl S l 1 l@l 0 ! 0 l 0 l 0 14 15 l u l 0 l 010101010 LICE Nbi NUMBE R 23 l@l4 2b IlLICENSE 11 1111 TYPE JO l@l57 Lail 54 l@
F 5{l} l L6J }@l 6101510 DOCKET l 0 l NUM8ER 0 l 2 l 81568l@l6il 017EVENT l 0 DATE l 9 l 8 l 0 l@l018 74 75 l0 l11810 REPORT DATE 80]@
EVENT DESCRIPTION AND PROB ABLE CCNSEQUENCES h 2l Transformer (T4) of DG-1 failed. This transformer fed oower to the diesel's nil uI Z, ! mersion heater as well as alarm circuitry corresoondina to the followina items: I Low lube oil pressure. Low lube oil level, and Hiah or low lube oil temoerature. I Il
]I During the time of the transformer (T4) failure, DG-2 as well as the 161KV and 345 KY gI systems were available and operable and would have been more than caoable of niti- 1
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lI catina. the circumstances of an accident should. the need arise. In addition. DG-1 l was considered inoperable only during the time that the transformer was being 1, changed out, i .e. only while DG-1 was in " local maintenance" s:
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A4 47 J2 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS g! The transformer failure was caused by a shorted coil. The transformer was reclaced I witn an equivalent component and subsequently the diesel generator, immersion neater gi and all transformer related annunciation circuitry was satisfactorily tested and l l g; returned to operation. The replacement transformer although eletrically eouivalent I gl was of a different manufacturer. Thus an exact replacement transformer or the transi
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P LER 80-014 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT N0. 1 Safety Analysis The Fort Calhoun Station Unit No.1 Engineered Safety Features System is so designed that no single failure can prevent the safe shut-down of the plant if necessary. During the time diesel generator DG-1 was inoperable, diesel generator DG-2 was operable as were the 161 KV and 345 KV supplies thus providing more than adequate capability for safe shutdown of the plant should the unlikely event of an accident occur.
It should be pointed out that DG-1 was considered inoperable only during the time that the transformer was being changed out since this transformer only feeds the oil immersion heater for DG-1 and associated annunciation. Should the need have arisen, DG-1 would still have automatically started per engineered safeguards and performed its -
design function as described in the Final Safety Analysis Report.
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. . a LER No.80-014 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT NO. 2 Corrective Action M.0. #6421 was written to replace the failed Westinghouse 480/120, 100 Va, Model 2-F-47-1 transformer. Since Westinghouse no longer manu-factures this transformer, (it was superseded by their model 1F0892) and no exact duplicate / spare was available, it was replaced using an equivalent GE 100 Va, 480/120 volt transformer. Upon replacement, the diesel was tested satisfactorily for operation as was all transformer related circuitry and the diesel DG-1 was returned to service.
As a further note, the Westinghouse model 1F0892 transformer which has superseded the failed model 2-F-47-1, and is electrically equivalent or superior to the model 2-F-47-1 has been ordered and will be installed in DG-1 circuitry as soon as procurement allows. -
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LER No.80-014 Omaha Public Power District Fort Calhoun Station Unit No.1 l Docket No. 05000285 i
ATTACHMENT NO. 3 f
i i Failure Data This is the first failure of this type at the Fort Calhoun Station.
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]l During the performance of ST-ESF-6, F.2, Appendix F, Diesel Generator #1 (DG-1) I gl failed 'to start on its secondary air system. DG-1 was removed from service in I gl accordance with Tech. Spec. 2.7(2)i and the secondary air start motors were re- I gl paired. Prior to the incident, DG-1 had successfully started on its primary air I gI s tart syste'a. In addition, DG-2 was started to verify its operability. I OI l I
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33 34 36 37 40 41 42 43 44 47 CAUSE oESCRIPTION AND CORRECTIVE ACTIONS gi The vanes of the air motors were stuck which prevented the motors from turnino. Thei gI vanes were cleaned, the motors were installed and DG-1 was successfully started on J gl its secondary air start system. To prevent future simil ar events, the air start I gl motors and the air line strainers will' be inspected and cleaned annually per I gi surveillance test ST-ESF-6. I 8 9 80 ST % POW ER OTHER STATUS 01 RY DISCOVERY DESCRIPTION
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-. J LER No.80-030 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT N0. 1 Safety Analysis Fort Calhoun Station Unit No.1 is designed such that a single failure cannot adversely affect the ability of the plant to be safely shutdown in the event of an accident. Although DG-1 failed to start on its secondary air start system, it had previously successfully started on its primary air system. In addition, DG-2 and both redundant offsite power supplies (161 KV and 345 KV) were available during the time that DG-1 failed to start on its secondary air system.
M LER No.80-030 Omaha Public Power District Fort Calhoun Station Unit No. I Docket No. 05000285 l l
ATTACHMENT NO. 2 Corrective Action l
M.0. #8169 was initiated to repair the secondary air start motors of DG-1. An inspection of the motors revealed that the vanes were stuck which prevented the motors from turning. The primary and secondary air start systems will be tested periodically per ST-ESF-6. In addition, the primary and secondary air start motors and the air line strainers on t
the primary and secondary aid start systems will be inspected and cleaned annually per ST-ESF-6. The air line lubricators on the primary i
and secondary air start systems will also be inspected annually and, if l necessary, they will be cleaned.
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LER No.80-030 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT N0. 3 Failure Data Previous related incidents are detailed in Unusual Event 73-5, Ab-normal Occurrence 75-20 and LER 77-12.
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