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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
LIC-90-0581, Informs That Requirements of NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount Satisfied.None of 48 Transmitters in Use at Plant Exhibited Symptoms Indicative of Fill Oil Problems Since Installation in 19871990-07-18018 July 1990
Informs That Requirements of NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount Satisfied.None of 48 Transmitters in Use at Plant Exhibited Symptoms Indicative of Fill Oil Problems Since Installation in 1987
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
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
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
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
ML20043G3281990-06-0101 June 1990
Advises That Personnel at Util Reviewed Reactor Operator Licensing Exam Administered on 900529.Comments on Exam Encl
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
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
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
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
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
ML20042H0021990-05-10010 May 1990
Fowards Fort Calhoun Station Performance Indicators,Mar 1990, Monthly Rept
ML20042G9981990-05-10010 May 1990
Forwards Proprietary & Nonproprietary Rev 13 to EPIP-EOF-18, Offsite Radiological Surveys.
1990-09-07
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Omaha Public Power District 1623 HARNEY s OMAHA. NEBRASKA 68102 m TELEPHONE 5 36-4000 ARE A CODE 402 March 13, 1980 Director of Nuclear Reactor Regulation ATTN: Mr. Robert W. Reid, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington,-D. C. 20555
Reference:
Docket No. 50-285 Gentlemen:
The Omaha Public Power District received a letter from the Com-mission, dated March 10, 1980, requesting additional actions orLin-formation concerning implementation of Category A Lessons Learned requirements at Fort Calhoun Station Unit No.1. The Commission's concerns are addressed in the enclosure forwarded herewith.
Sincerely,
.i){k ~
W. C.' Jones Division Manager Production Operations WCJ/KJM/BJH/TLP:jmm Enclosure cc: NRC Regional Office LeBoeuf, Lamb, Leiby & MacRae 809 5
///
8003240 3 7 3
..~ "..
- p Enclosure 1 RESPONSE-T0 REQUEST FOR ADDITIONAL ACTION / DISCUSSION-
. LESSONS' LEARNED . CATEGORY A Request:2.1.1
. Implement procedures for manual reconnection of pressurizer heaters prior. to restart of Cycle 6.
Action / Discussion Procedures for reconnection of the pressurizer heaters have been
. completed and added to the appropriate emergency procedures.
Request 2.1.3.a
[(1) Document your connitment to power all valve position indi-
'cators from one vital bus at least until equipment qualification is -
complete'.
-(2)- Equipment must be operational prior to restart for Cycle 6.
- (3) Modify emergency procedures to reference new valve position indicators.
- Action / Discussion (1) Prior to restart for Cycle 6, all valve position indicators for power operated relief and safety valves will be powered from one
.vi tal ' bu s. Power feed to one-half the indicators will be changed during the 1981 refueling outage. ,
(2): All position indicator equipment will be fully operational prior to startup, Cycle 6.
(3) 'The acoustic indication of the status of the power. operated relief valve will be added to the symptoms section'of.the appropriate emergency procedures prior to startup.
Request 2.1.3.b~
(1) Provide plans-and schedule for upgrading sub-cooling meter temperature inputs.
.(2) Discuss capability to monitor sub-cooling' margin with the plant computer (core exit thermocouple inp~u ts).
(3) -Modify emergency procedures-to reference new sub-cooling
~
. monitors.
(4) ' Equipment must be. operational prior to restart of Cycle 6.
1 g =
1 1
, Action / Discussion
.(1) The . temperature inputs' to the subcooling margin meters will be -
upgraded to~ the 300.to 7000F range during the 1981 refueling outage.
(2) -The subcooled margin can be monitored with the. plant computer _
using the core-exit-thermocouples. It is proposed the saturation tem-
- perature be calculated using the RCS pressure as an input. This tem-
- perature will be compared to the average of eight core exit thermocouple temperatures and the degree of subcooling displayed to the operator.
(3) The subcooling marg'in meter and ' alarm indications will be-
- included in- the appropriate operating instructions and emergency pro-
. cedures prior.to .startup.
(4) All equipment will be fullyfoperational prior to restart of
' Cycle 6.-
Request 2.1.4 (1)' Revise your December 31, '1979, submittal to clearly identify
- essential and non-essential systems. ,
(2) ~ Provide the bases for your classification of essential systems.
Action /Diseussion-Response to this request is provided in Attachment A.
-Reques t ' 2. I'. 6. a Final- system leak rates measured during~ the leak reduction program must be obtained prior to Cycle 6' power operation and reported shortly thereafter. .
Action / Discussion Final system leak rate measurements will be obtained prior to Cycle 6 restart and the results will be reported within two (2) weeks fol--
lowing restart.
Requesti2.1.7.b Your safety grade auxiliary feed flow transmitters and steam generator: level transmitters must be installed prior to startup.
- Action / Discussion 1 All' safety grade auxiliary feedwater flow transmitters and steam
=-
generator level. transmitters will be~ installed prior to Cycle 6 restart,
- providing the one ^1evel transmitter -that was returned to the vendor is.
^
. received in time for Cycle 6_ restart.. The transmitter is due to be-l- shipped . March -13, 1980.
i ,e4.- , , - - , y , ,- ,.
4 -s -
~
iRequest2.128.c Incorporate the procedures for-determining airborne radiciodine concentrations in occupied: areas following an accident. Procedures should reflect need to move sampler.between Technical Support Center and Control Room.
Action /Diicussion 0perating Instruction OI-PAP-9, Procedure for Post Accident
. Monitoring of Radiciodine in Occupied Areas, has been completed.
Instructions for instrumentation operation and personnel actions in the
. . control l room andLTechnical Support Center area are includa'
. Request 2.2.2.b (1). Revise Emergency Plan .to designate dedicated channels on the GAI-TRONICS for communication between the Technical Support Center and the Control Room and the Technical Support Center and the Emergency Control Center.
(2) Revise. Emergency Plan to designate an Emergency Duty Officer as the Technical Support Center Coordinator.
(3)~ Commit to a date for operational condition for the computer-display of plant parametens inside the Technical Support Center.
Action / Discussion (1)1 A revision to the Emergency Plan, section 5.3.1.1.1, has been initiated that'provides for channel 3 of the GAI-TRONICS system to be dedicated for communications between the control room, Emergency Control l
~ Center-(ECC), and the Technical Support Center (TSC).
(2) A revision to:the Emergency Plan, section 5.2.2.2.2.1.2.c, has been initiated to require that, upon a second Emergency Duty Officer !
'(ED0)' reporting to the ECC, one will remain at the ECC and the other l will report to the TSC to act as TSC Coordinator.
(3) ' Computer display of plant parameters in the TSC will be operational within 30 days of-plant startup following Cycle 6 reload.
^l 1
I
Attachment A-
> LRequest 2.1.4, Containment Isolation The Fo'rt CalhounlStation Unit No.1 reactor containment building is provided with an automatic. actuation system which operates containment penetration isolation valves (both to the open and to the closed posi-
-tion) to mitigate the consequences of an accident. The automatic systems are the Containment Isolation. Actuation Signal' (CIAS) and _ the Ventilation Isolation Actuation Signal (VIAS). It should be noted that VIAS is.
redundant to CIAS in that-it also generates a valve closure signal for certain isolation valves. closed by-CIAS; specifically, the containment purge and relief lines.
.The CIAS, as well as Safety Injection Actuation Signal (SlAS), is generated if either a Pressurizer Pressure Low Signal (PPLS) or a Con-
.tainment Pressure High Signal (CPHS) is generated by an accident con-dition'in the primary system and/or containment building.- The actual mechanism of isolation is designed to meet single failure criteria. The
.CIAS system consists of two redundant isolation channels (or trains) which are actuated by sensors, in a two-out-of-four logic, monitoring
, the primary system-and containment pressure. When the actuation logic l
is satisfied, a signal is then generated which actuates the PPLS or CPHS "86"~1ockout relay which mechanically seals in the accident signal. The accident-signal in turn actuates- the emergency core cooling system and CIAS via an "86". lockout relay which mechanically seals.in the CIAS
- control function. In addition, the Fort Calhoun Station Engineered Safety. Feature System is provided with an additional control relay whereby Channel A control may " reach across" and actuate Channel B e'q uipment and vice versa. This provides increased availability of safety equipment. . The CIAS train separation is maintained at the line
- isolation valves; Channel A will operate the A valve, and B the B valve
.(exceptions are dealt with later in the discussion).
l When the "86" CIAS relay is actuated, relays in the CIAS panel AI-
.43A and AI-43B are de-energized, causing the isolation valves to assume Jtheir accident position. In general, this electrically de-energizes a seal.in control' relay, which in turn de-energizes a solenoid valve which i
allows the air operated diaphram to go to zero pressure closing the l valve.
The.previously discussed circuit is such.that when the accident signal is reset the valves remain in their accident positions. The i- valves may then be manually reset valve-by-valve (or pairs of valves as in.the case of certain cooling systems). No group resets exist. In
~
addition, in general'when the accident signal is present manual re-positioning of the valves is blocked.- Exceptions will be dealt with in the following discussion of essential and non-essential ~ systems.
- , . - . . ,__ _ g- , . . -
v- .
a' _
^
s J
~
= -2 '
V NON-ESSENTIAL SYSTEMS
_ 4.
u -{
! System & Function "
Isolation Valves .~ Reason for Isolation
- ._1h : Primary System Letdown .
~
- HCV-204, TCV-202 ' Direct Connection with
~
-RCS
. -**.:2.- Roactor! Coolant Pump' HCV-241,--HCV-206 -Direct Connection .with Bleedoff RCS
*S 3 . S1 Tank Cooler Flow.
~
--HCV-2983 ' Direct Connection with s
~ RCS-
- :4. ReactoriCoolant: Sample HCV-2504A,LHCV-2504B Direct Connection with
-RCS
.5. ' Containment Sump ~ HCV-506A, HCV-506B Direct Connection with Containment Atmosphere
- 6. ~ Reactor Coolant Drain . HCV-500A, HCV-5008 Direct Connection with Tank' Discharge'. Containment Atmosphere
- 7. - Makeup.to Pressurizer _ HCV-1560A, HCV-1560B Potential Connection to Quench Tank RCS.
- 8. Demineralized Water - HCV-1559A, HCV-1559B Direct Connection with Supply. Containment Atmosphere
- 9. RCl Drain Tank Vent HCV-507A, HCV-5078 Potential Exposure to
'DBA Conditions 1
~10. ? Pressurizer Quench - HCV-509A, HCV-509B Potential Exposure to
-Tank Sample Line DBA Conditions
-11. .RC Drain-Tank Sample. HCV-508A, HCV-508B Potential . Exposure to -
CBA Conditions L12. -N2 Supply . HCV-2603A,.HCV-2603B' Potential Connection with Containment Atmosphere
~
113./N'Supplyto, 2
Pressurizer ~HCV-2604A,'HCV-2604B Potential Connection with Quench Tank- Containment' Atmosphere
.14. 1 Containment Radiation PCV-742E .F, G H Direct Connection to Containment Atmosphere L.
+
J15i t Containment. Relief' HCV-746A., HCV-746B - . Direct Connection to L < ,
Containment: Atmosphere n . 16. ! Service Air HCV-1749 (inboard Direct; Connection to-valves are manual Containment Atmosphere L
closed)
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- - NON-ESSENTIAL' SYSTEMS (Continued)
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" System & Function Isolation Valves Reason for Isolation
.17; Containment tir; Purge'- PCV-742A,' B,-C, D Direct Connection to Containment Atmosphere
- 18. Nuclear Instrument HCV-467A, B, C, D Closed on Containment Detector Well Cooling Isolation
- 19.- SI: Leakage Cooler HCV-425A, B, C, D Closed on Containment Isolation 20.. Blowdown (SG)- HCV-1387A/B Closed on Containment HCV-1388A/B . Isolation
- 21. Blowdown Sample (SG) HCV-2507A, B Closed on Containment.-
HCV-2506A, B. Isolation
*HCV-2983 receives an isolation signal from both trains of. CIAS.
The remaining valves associated with this penetration are closed by-a safety injection signal and are part of the safety injection /
leakage cooler- pressure protection: system.
' ** Control switch will reposition valve with. accident signal present; however, will immediately reclose when switch spring returns to
-normal.
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4 The remaining valves discussed in this section'are provided with a
~ containment isolation signal; however, in order to provide maximum flexibility, operation differs from the previous discussion. ' Those--
isystems . considered essential and the justification for. this designation -
are.specifically0 called out within the text.
-1. :The~ instrument air header valve PCV-1849 closes on low air
. pressure (70:psig)andCIAS. With.a normal operating pressure
- above accident: pressure, the air header isoleft in service unless low air pressure-is detected.- The availability of air
- enhances reactor shutdown. It must.be emphasized that air
~fai. lure will.in no way inhibit shutdown. -PCV-1849 fails open.
2.
- The hydrogen purge system ^HCV-881, 882, 883A/C, 884A/C is required for~ operation ~1n a post-accident condition. The L supply and ~ exhaust, ~HCV-881~.and 882, are equipped with auto-matic valves inside containment only.- These valves are closed
-by CIAS, but fail:open on loss 'of control power or air. The valve isolation function'is backed up by redundant locked
~ closed manual valves. 1The sample valves,-HCV-883A/C and HCV-884A/C, have a similar arrangement; however, the automatic valves outside containment, HCV-883A and 884A, fail closed and
.are closed by.CIAS. Override switches are provided to over-
~ ~
ride the CIAS function. The system is used to detect and
. remove hydrogen in a post-accident environment.
- 3. The auxiliary feedwater system (hhich is not directly con-nected to the RCS or containment atmosphere) HCV-1107A/B and 1108A/B are opened'by:CIAS and fail open.' 0verride switches-
.are provided for post-accident valve positioning. Circuit modification to these valves will be dealt with under the
. Auxiliary Feedwater Section of NUREG-0578. This is considered a,n essential system because it provides for decay heat re-moval.
- 4. The main feedwater' penetration isolation valve HCV-1385 and 1386 are motor operated valves which close on CIAS. These valves -fail "as~ is", but are connected to a vital 480 volt bus to ensure closing. -In addition, there are check valves 'in the system as redundant valves. This system-is.not directly connected to,the RCS or. containment. atmosphere. To enhance the ability ~to mitigate a small break LOCA, a design change is being evaluated to provide automatic isolation of HCV-1385 and HCV-1386 on.CPHS or SGLS, similar to the main steam isolation 4 valves. It should ~ be noted that decay heat removal' may always be accomplished by auxiliary feedwater. The availability of main feedwater will enhance accident response ability to
- . remove-decay heat in'some accident situations. With an
. a.ccident signal- present, if an attempt .is made to open: the
' valves manually, they will drive open then immediately back closed.
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- 5. ' The containment air cooling units' cooling water supply valves HCV-400A/C, B/D, 401A/C, B/07_402A/C, B/D, and 403A/C,-
~ B/D are opened by CIAS and. fail open. :This is considered an essential system. This system functions to limit containment pressure...
- 6. The reactor coolant pump lube oil: cooler and seal cooler supply and. return line HCV-438A, B, C D close_on CIAS._ The valves inside containment (A and C) fail open. The valves have override switches to' open after CIAS to reinstate cooling water. 'The failure of valves or closure on CIAS-will not trip the reactor coolant pump motors.
The remaining penetrations not actuated by CIAS 'are those which are a_ssociated with shutdown or a different type accident. These systems are listed below.
-1. Safety injection - opens under accident signal. This is considered an essential system, which supplies borated water to the reactor core.
- 2. Containment spray - opens on CPHS and PPLS. This is con-sidered an essential system to limit containment pressure.
- 3. Shutdown cooling - locked closed,'it functions as part of the RHRS system.
- 4. Containment sump recirculation - part of ECCS actuates on RAS.
This is considered an essential system, 'since it functions as part of the post-accident heat removal system.
1
- 5. Main steam isolation valves - closed upon SGLS (Steam Gener-ator Low Signal) and CPHS (Containment Pressure High Signal)
~
part of closed system not in contact with RCS or containment
' atmosphere. They function to mitigate a main steam line break
. accident.
~
6.- Charging - does not isolate. This is considered an essential system that provides boric acid 'to the core. This system is not considered in the safety analysis, but helps assure plant safety.
- 7. Containment pressure monitoring penetrations (4 total) -
remain open, generate CPHS. They allow for monitoring con-tainment pressure.
- The design' requirements of NUREG-0578 are presently satisfied, and i no changes' to the initiation scheme or to the circuit design are neces-- I sary.-. The ' deletion of HCV-438A, B, C, and D from CIAS closure is under evaluation; but this will not affect the isolation requirements of-
.NUREG-0578. Essential systems, identified above, are those which are not~ isolated on CIAS. All non-ess c tial systems are isolated.
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