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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 e OMAHA. NEBRASMA 68102 m TELEPHONE S36.4000 AR E A CODE 402 July 14, 1981 -
4 Mr. Darrell G. Eisenhut, Director Q U. S. Nuclear Regulatory Commission f: g4 d Office of Nuclear Reactor Regulation 6 g 7 Division of Licensing i h /j>
Washington, D.C. 20555 Y.O d' y/
Reference:
Docket No. 50-285 bke _. aie'/
Dear Mr. Eisenhut:
In response to the Commission's letter dated February 10, 1981 (Generic Letter No. 81-14) regarding seismic qualification of the auxiliary feedwater (AFW) system, Omaha Public Power Districc submits the attached report. The attached evaluation report (Attachment 1) on the seismic qualification of the auxiliary feedwater system was per-formed for the District by Gilbert / Commonwealth engineering consultants, and the results and recommended actions are summarized below. Attach-ment 2 provides a sunnary listing of the qualification status of each AFW component.
Qualified personnel experienced in the analysis, design and evalu-ation of the AFW structures, systems, and components performed the walkdowns to identify potential seismic deficiencies of the system.
From these wali.down inspections Gilbert / Commonwealth (G/C) has concluded that our AFW system (including mechanical and electrical equipment and components including battery racks, co'*.rols, instruments, motors, compressors, tanks, electrical supplie and the cabinets containing these items) is seismically qualified except for the four deficiencies outlined below.
The four identified deficiencies, along with the planned corrective actions, are as follows:
- 1. Electrical Supply Conduit to the AFW Pump FW-6 Motor--The conduit was found to be inadequately restrained. An addi- /g/ yg tional support will be added by the end of 1981 to increase 3 j
the conduit resistance to seismic movements.
- 2. Valve Operators on Small Bore Piping--The current operator supports were found to be unstable. Modification work will involve removing the existing support rods and replacing them with a more stable support by the end of 1981.
- 3. Small Bore Piping (Cold System)--The rigidity of this piping was found to be inadequate due to improper support spacing.
Pipe restraints will be added as per the G/C recommendations by the end of 1981.
8107230015 810714" PDR ADOCK 0500028F P F D<
Ln Mr. Darrell G. Eis:nhet, Dircctor July 14, 1981 Page 2
- 4. Small Bore Piping (Hot System)--The rigidity of this piping also appeared to be inadequate although the high operating temperatures (3500F) of this piping makes it critical to consider potential negative impacts of additional restraints on thermal displacements and loads. The District is currently perfonning a detailed pipe stress analysis to determine detrimental impact of additional pipe restraints. This analysis is expected to be completed by September 30, 1981.
Modifications as needed will be completed by the end of 1981.
After the four deficiencies have been modified, the entire AFW system will provide. substantial resistance to movement cessed by seismically induced forces. Since the schedule for resolving these deficiencies is consistent with the schedule for the overall upgrade of the AFW system, as required by NUREG-0737, the District believes there is adequate justification for continued plant operation.
Sincerely, l
\!
I 6)(
W. C. . ones Divisi n Manager Production Operations WCJ/KJM/TLP:jmm Attachments cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C. 20036
' Gilbert / Ccmmonwezith rs t Aewn w .2 w w se .
INSPECTION FVALUATION REPORT The following is an evaluation report of the inspection performed in response to the NRC's Generic Letter No. 81-14 (OPPD Task ES-81-01) .
Upon investigation of the Auxiliary Feedwater (AFW) System it was determined through the use of Piping and Instrumentation Diagrams (PSID) that the AFW system is seismically qualified. This system was included in the inspection and analysis performed within the scope of the NRC's I & E Bulletins 79-02 and 79-14. The remaining mechanical and electrical equipment which was not included in Bulletins 79-02 and 79-14 was inspec-ted and deficiencies were numbered and red tagged for identification.
There were only four areas in which the inspection indicated defi-ciencies.
- 1. Electrical supply (Conduit) to Auxiliary Feedwater Pump FW-6 motor: The conduit was not adequately restrained seismically. The recommendation is to add a support to increase resistance to seismic movements (see Attach-ment 1).
Support No. Sheet MW-5 253
- 2. Valve Operators: This deficiency is for the valve operators on small bore piping. The operators supports were found to be unstable as currently installed. The recommendation la to modify existing supports (see Attacinent 1).
Support No. Sheet AFW-1 2&3 AFW-15 6&7 AFW-18 6&7
9 E SMbert/ Commemmeath
. acsan e .emaoem
'Page 2 INSPECTION EVALUATION REPORT 37 Pipe rigidity - (Cold. Systems): This deficiency involves small bore piping 2 inch and -smaller which was not with-in.the scope of the NRC's I & E Bulletin 79-14 and was, therefore, not analyzed or inspected during the bulletin work. - This piping was inspected and evaluated within the scope of this work to comply with the NRC's Generic Letter No. 81-14.
The evaluation of this piping was based on frequency, rigidity, and stability of the system during inspection.
- The frequency of the piping was analyzed using a nomograph
. furnished by the District, which was the original design basis of Gibbs and Hill Inc. during construction.
Using this nomograph (see Attachment 1, Sheat 8) the supoort spacing was found to be inadequate to achieve first mode fre-quencies' of 18 CPS for vertical and- 6 CPS for the horizontal.
The following support modifications and additions are recom-mended to increase rigidity under seismic conditions. Also, the relative frequency is estimated for both as found and with proposed modifications (see Attachment 1).
Support No. Sheet AW-2 2&3 AFW-3 2&3 AFW-4 2&3 AFW-6 2&3 AFW-7 2&3 AFW-8 2&3 AFW 2&3 AFW-10 2&3 AFW-ll 4&5 AFW-20 6&7
r _ _ - _ - - - _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ __
1Mbert/Commemmeseth xe n see.e.a.ma aa,m.a m
'Page 3 l
INSPECTION EVALUATION REPORT
- 4. ' Pipe Rigidity .(Hot Systems): The same analysis was done on additional piping of the same description as item No.
3 above, with one important difference. This piping could reach or operates at temperatures above 3000F. At these temperatures it is critical to consider thermal displace--
ment and thermal loads.
Due to the complexity of the piping involved, which appears to need additional supports for rigidity, G/C recocnends that a detafled pipe stress analysis be performed for the '
steam drive and condensate portions of the Auxiliary Feed-
. water piping associated with pump FW-10. This analysis
'should be performed to assure that additional supports do not have a -detrimental thermal impact on the system. The following. support additions should not be incorporated until approved by pipe stress analysis (see Attachment 1).
Support No1 Sheet
'AFW-12 4&5 AFW-13 4&5 AFW-14 4&5 AFW-15 4&5 AFW-16 4&5
^
AFW-17 4&5 AFW-18 4&5 AFW-19 4&5 AFW-22 6&7
, All other mechanical and electrical equipment and compo-nents including battery racks, controls, instruments, motors, compressors, tanks, electrical supplies and the cabinets containing such items, associated with the Auxi-liary Feedwater System were found to be securely attached to.tbeir supporting structures, such that substantici resistarce to movement. caused by seismically induced forces would be'provided.
.s
e "
/ ,
aos : *.egs a .- a a Page 4 1- INSPECTION EVALUATIDd REPORT _
This inspection and evaluation was accomplished using personnel exper-ienced in the analysis, design, and evaluation of structures, systems, and components. .These personnel were familiar with the plant and the require-mnts for other seismically qualified systems. This was due to their
-direct involvement with the NRC's I & E Bulletins 79-02 and 79-14.
. Asidescribed previously, all large bore piping (21s and larger) assoc-
This piping was analyzed during the work performed as a result of the NRC's I & E Bulletin 79-14. The analysis of the Auxiliary Feedwater piping and as'sociated~ equipment was accomplished by the dynamic computer code entitled
- T-Pipe. The appropriate response spectra, as described in the Fort Calhoun Station Unit #1 Final Safety Analysis Report (FSAR), Appendix F, Section F.2.5, was used as input for the seismic analysis. Also, the loading com-binations and stress limits used for analysis were taken from the FSAR,
. Appendix F, Table F-1. Detailed information concerning input and analysis results are available through Gilbert /Comn.anwealth's documentation of the 1
NRC's.I "ulletin 79-14.
Also, includedlin this evaluation are the support designs which were requested by the District, and are associated with the Auxiliary Feedwater system. .These supports were-designed in order to replace mechanical anub-bers with Hydraulic' Snubbers (see Attachment 1).
4
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' Commcruea@ DESIGN OF PIPE SUPPORT Ccmpames SHEET _ OF R&v6EW BYiOATE Adwiliaev Fe, Awafe e- Boos so. Attels. 1 lREV.
Tabula 6n h anal ysis of dn.degodecl leng+ks of small bore p', ping 8er evalcistien of Adxiliary Facclwafe.- 6ys.lem.
hr Valdes are 2", l'2 and I" f line s will, d wiH,od f insulatien.
(14. - 18) (6- M K l va'lde lisirw3 Freq0ency l Wetica1 decir.onta 1 2*/,sch.Ao, w/o insulatien Feef- Avg. Feet Avo . I 6- 6 1417 to'- 8'2' (1'.19' F- 6 22(2 (3'- 11'2 (2' 21'- 181' 2d F-F 3222 ts'- 14' 2G'- 24' 2"4,sch.do, w/ 'inodlalien '
6-6 189 9 9' - 8' 19'- 14' F-6 1809 12'- Id 11' 19'- F1'd 18' P- F '2G 35 15'i- (2'i 22'i- 21' l
[I2~ , F31. 40, w[o en$dishion 6-6 It91 9' l'd 19'.iA' F-6 l19 1 t2'- t o' II' 19'- t 8' i8' I:- F 2418 14'- I2'i 23'- 21' l'2'd,6ch.Ao, w/ inedlation 66 885 S' l' lis'- (2'2' F- 6 (5 l'1 Id- 8'd 9'2 ' tT-tr/ tG' F-F 2ee8 12'i- I t ' 2d- IS'd I'/,ecl.4o, 3 w/o insula tion 6-6 Sc9 8'- T IS'- (2' F-6 1269 cl*- 8' cl' ic.'- id ' 15' i
P - P' (841 (2'- Id Ict '.16' l'd, scis. Jo, w/ insulshon 66 @80 G'2'-6'I t l ' - I c' F6 9o(, S' - 1 ' 8 (4'- (3' IS' FF \$10 Id - 8'1' IG'- IS' Above (VQ valdes fabdlafed accord;ng do e end co n di fio ns-binvie hele Fixe d h ele Piggd - FiAtb
, - = + . , - - - - - - - - - , - . - , , . - . . ,,,,..-..--,-w,,.y -
,y y,w.- ,.g-yy.,y, . , , ...twwv'*wm,ym--- _W e- -
-NgN-"-y--'--=e-e==e-y ---T- -
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[ ] Commnnwealth Associatas Inc.
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pO ER D TRI FT. CALHOUN, UNIT 1 64c285400 hiCe4 C ALC, SY/DATE SUBJFCT i CcmmonAea@ DESIGN OF PIPE SUPPORT
. Comcanies aEview aviOATE SHEET NF REV.
80 fro 2T fi /s Feaqde,acy 12eou 6drecer Wd nqi/E st %ze Wo. 6:ecgE/AWcv AF -I l '2 Y N/A N Olve cP*rdto" i* d" stable in tJ direction AFW -2 l'2' / S.6 19 dn6dpfortec5 riser bran (t2')
AFW-3 l '2" M d/A 19 d.6 elf is not resfraindq [Agd AFW 4 l'2N 9.9 l'1 dnedryerfed riser $pon (I4')
Ar=W 9 7"p conduit W/A 19 dwr io dnefable in 60 direction
~ '
Af W - fo l'24 7.9 94 dneurrorted riser cysn (12'2)
~
AFW-7 l's 4 9.9 81 dnsoryorted riur sgan (11')
AFW 8 i 'C' 4 ll.o 8) dnedpforfecI run 6psn ( lo')
AF%l -9 2" / '5.9 8' dnoopycried cernb. riser 5 run (2l'i)
AFW - Io '2"/ 8.9 96 dnsupperted riser span (15')
t
OMAHA PUBLIC
[ ] Commnnwerith Associat s Inc.
. 4 .. ./-cu.a.
POWER DISTRICT FT. CALHOUN, UNIT 1
,c no. 64o285400 Gee CALC BY/DATF SUBJFCT Commcnwealth 3mpames REylEW SY/DATE DESIGN OF PIPE SUPPORT 3ggg7 3 g, 9 Ng LY [ nev.
N N
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$dffol21 AC. Vd0fottQ (Mc9tFC CAftosJ AFW-I 8erv,ove existing red i replace w/ +fedt A Fi4 *2 Add pipe resfrainf in the (v. 4 m) clireclions increasing kre(dency to = d2 ( reduce *F8" I* G' A FIA 9 Tightsi, d.16 elf do re+frain pipe AFW-4 Add gig resfraint in fhe (t ? 7.) directions increasing (Werk w/ AFW-li) fregdency lo :: So i redJce span lo ~1' AFW-9 Add reefraini fe conclait in the G) clirecfien
! AFW-6 AJJ rire reofraini in ihe (x i a) direc3 ions increa+ing '
(Werk w/ AfW*) freqdency to 2O f rec ldce Span fo (o '2 l
l AFIA -1 Add pipe restroint in the (x) direction cm run a bove rise r l increaeing s frequency fo % % h reddca 6ran to II' APW-8 AJJ give restraint in, the (a) direcfien increasing frequency f'o Al ? redace span lo 9 l
AFtJ-9 Adcl directions ai AFW giye1 restraint location- incerasig in the (x i y) jregdency to i = 29 { reddce +gan fo lo' l
l
^
AFIA 10 AJJ pipe erotroinf in , the (x i r.) Jicecfion* increasing to e 94 f redace sgon lo C2 (work w/ freqdency AFW-6)
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] Commcnwedth Associates Inc.
ms -= v.m .a.
pO ER D TRI L
FT. CALHOUN, UNIT 1 644285400 CALC. S Y,'O ATE SUBJE to nwegg DESIGN OF PIPE SUPPORT SHEET oF (cmames y REVIEW BY/DATE
[nev.
6erroef five Faaedaucy foom 6dvroser Llornber Site ido. 9 scigeFAWCY A F W -11 2" p il 19 dnsopported comb. riser i run (n'2 )
2' /
AFWt2 Insulafed 4.9 ici da*erveried comb. riseri run (is') l l
2*f :
AFW-l+ Insulafed M 81 Ex;ehncy supperf is dnefabla l
e"#
AFW-14 (nsulated 6.9 Si dnedygerted eun cyan (id')
AFW -19 2" 4 4/A Si Va' lve operator i* dnsfable insulafed in (x) direc4iert :
AFW - IG 2'/ Le* tl'an 81 dnsoyerfecl run epsn insulated 2 (to') Vert f (2T) lloria.
t*f Lt.s % sn AFIA- t 1 Insulated 2 81 Idorb w/ AFtJ- l(o !
I i
)
AFLJ - t6 2- 4 W/A 81 V'alva oper.rAor is onedable l (x.) direction Insulated in i
A F W -Ici 24 3.9 SI uneuFForted comb. run !
Insulateel ri+tr (n')
~ _-
.____. _ _ __ ._ _ _ ____ _ ___. _ .- __ _ _ ____ -..__-__________J
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[ ] Commonwe.atth Associat:s Inc.
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pO ER D TRI
./.m ..u.
FT. CALHOUN, UNIT 1 64c285 coo ca c.svioare sus;
@ S&tes RE VIEW BY/DATE Aonib,y Feedwa+c,- ,00, so Mch 1 bJ N 's hY [ aav.
a \x
-ferroer kJo. 9sorcego tilove/ICA1'ICW J
AFW- II Add pipt restraint on riser in (x i a) directions ,
increasing DJack w/Af*4) frquency to = 47 f redoce +ran lo s'2 AFW 12
- Add giFe retfroint in (a) direcf;on increasing
%dency to e fo ? reduce 6ron lo l '2 '
AFW-19 demow exi+1ing +0rrert h replace w/ new (xiy) reefraint AFW-14* Add pipe reofemin4 in (x) diradion increa$ig
%dencylo= 22.9 ? reduce span lo T AfW 19 femove rod re+fraint i replace w/ Mrol in (x) direc4 ion AFW-16
- Add pipe re+trainf in (x i a) directions al 2 p*. f i in (y) , direction at i pf. increasing %oency to
= 14 ? recidce span lo @
=
AFW n* Add pire ec+fraint so worb w/ AFW- IG AFtJ - (8 Ifamon rod re+frainf i replace w/ +1 rot in (x) direc4 fen AFW- 19 e Add ein er+4rairst in (a i y) clic clions increasing ,
% dency l o e 19 ? redace span fo 8'2
- n Add only after detailed pigt *Mnr>+ analyois v.- - - w-.e--me--*-g--,.--.+,y y- -,--.v----. 9-9ym,,,w,,em ,.,,,,w,yy,mg-,,ywm,_.w--we---,v--ep--,p------mv,----w--m+--y,,
-py-wm-- --+yr,ywy-ey.-+-p,,._y-y,-y,w--w,,gy,-,gmw---
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[ ] Comm:nwsdth Associates Inc.
pO ER D R L
a*d"""/"* * *""
FT. CALHOUN, UNIT 1 64c28sao C E%eac DESIGN OF PIPE SUPPORT G 9 gggg7 n,
( Ccmcames j REVIEW BY/DATC l nsv.
id/folff IIfE ICEqdeWCY doet 4 hd/fcM Mumbat 617.E W o. bi4cCE/AWc.Y AFW 7o . 2' p W/A 81 Valve l>ypass i+ dnsfable in %e (a) direcfien AFW-21 2" 4 W/A 19 Yalve oprafer is dnsfalsfe (n+olafed in ne- (a) chrection AFW-77 l'/ 2.0 19 dnsegrerted riser span (fo')
AFy'- 23 2'M W/A 81 of RG reque+f to remove Insulated machen; cal $ndbber f replace w/ dyclemulic endbber f.gfnyfif Cesign 6-t 1
AFW- 24 de[tr do AFLJ 73 ff.efrofit dc+lgn 62 AFLJ- 29 # fofro[if desyn 63 6/er Io Al W 75 AFW-2G 6[er to AFW-23 Refrofit design 64 l
i AFW-27 k'ar fo AFLJ 23 fafr.fil de+ign 39 l
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] commonwzatth Associat:s Inc.
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pO FT. CALHOUN, UNIT 1 RD RI 64c285cco
" ' ^
C onweac DESIGN OF PIPE SUPPORT SHEET GF REVIEW S YIDA(E (Comcames j ,
MN hY l aEv.
s E X N H (!C t f d o. Vdofo@BG YModiftC.AftoM AFW 20 &mov'e exi+fing red j nrF ac8 l */'Ardl AFW - 21 fam.x exishng ved { replace w/ sfM AFW- 22
- Add yiye reedraint in (a) direction on rieer.
Other reelesin45 required AFW-29 & design 6ogyorf : 6 move exi+4iq mecksnical 6ndWer
? (SplaCG w/ hydredlic 6Mdbfper
((fecip complete es 0 l AFW- 24 6ce AFW-23 (6 2)
AFW27 6et AFW-23 (6. @
AM% bee AftJ 23 (6-4)
AFW 27 6te AfW -23 (69)
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- 3. ,.,r,,,.,---v--- , ,y, ,- w-,yw w-w-v w-g wg we y , ,.pr-+w-.9--y,w9y ..r-.w r- . m_.-y., p.,%%,-,- gm.---w gyy --. y-- -.- m_ - -
- f. 4- -
-- Attachment 2
SUMMARY
OF AUXILIARY
- FEEDWATER SEISMIC QUALIFICATION (1) Pumps / Motors - Adequately restrained for seismic qualification.
(2): Piping .2" diameter and under piping requires additional restraint to-be seismically qualified.-
.(3)f Valves / Actuators - Some valves and actuators require modifications
' to-their restraints to be seismically qualified.
~ . (4) ~ Power. Supplies ~ - One span of conduit was identified as needing additional restraints to be seismically qualified.
(5). Primary. Water and Supply Path - Storage tanks, major components, and structures are seismically qualified except as noted in items (2),(3),and-(4).
(6) . Secondary Water and Supply Path - Not applicable to Fort Calhoun
' Statforr Unit No.1.
i(7) Initiation and Control System - Instrument air tubing is adequately restrained seismically.
(8) Structures Supporting or Housing ~These AFW Items - Adequately restrained and sturdily. constructed for seismic qualification.
.yo
