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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
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. ' Omaha Public Power District i
.1623 Harney Omaha, Nebraska 68102 2247 40T/536-4000 J
i May 7, 1990 LIC-90-0361 .
?
U.- S. Nuclear Regulatory Commission [
Attn: Document Control Desk
' Mail Station P1-137 .
. Washington,-DC 20555 l,
L
References:
1 ~. Docket No. 50-285
'2.-. Licensee Event' Report 90-006 dated March 28, 1990 ,
(LIC-90-0246) ,
, <3. Letter from NRC (S. J. Collins) to OPPD.(W. G. Gates) dated i-March 20, 1990.
l-r c Ger.tlemen:
L
SUBJECT:
Diesel' Generator / Low Pressure Safety Injection Pump Interlock Feature l'
Reference 2 described an event which occurred at Omaha Public Power District's
-(OPPD) Fort' Calhoun: Station, involving a loss of .off-site power and Diesel L
Generator (DG) actuation. During the event, a low Pressure Safety Injection
.(LPSI) pump breaker. interlock functioned as designed and prevented the diesel .
from automatically energizing 4160 volt bus 1A4. OPPD committed to re-evaluate. .J the interlock feature and provide results of the evaluation. i L -0 PPD has completed an analysis' and calculation which; '
L .
L e -indicate that the DG/LPSI interlock is not necessary, a did not identify any applications similar to.the DG/LPSI interlock-which would prevent auto closure of the diesel output breaker under comparable circumstances, and i
- m. found that ' dead loading the diesel generator with any one of the LPSI, High Pressure Safety Injection-(HPSI), or Containment Spray (CS) pumps (which are prevented. from load shedding when manually started) is acceptable.
The main text of the Engineering Analysis (without attachments) is enclosed.
9005110170 900507 PDR ADOCK 05000285 i P PDC
-4s ser4 Empioumengn En sai opportunitu l' i
1 1
Document Control Desk LIC-90-0361 *
.- Pag 6 2 OPPD has' initiated a modification to permanently jumper the DG/LPSI pump
. interlocks.. This modification will be completed by the end of the 1991 refueling outage. Procedures will be revised as necessary upon completion of the modification.
If you should have any questions, please contact me.
Sincerely, t
W.
W. G.. Gates Division Manager Nuclear Operations WGG/mc-Attachment p c: LeBoeuf, Lamb, Leiby & MacRae 1:
A. Bournia, NRC Project Manager R. D. Martin, NRC Regional Administrator, Region IV P. H. Harrell, NRC' Senior Resident Inspector l
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EA-FC-90-027 Rev. O r
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1.0 PURPOSE The purpose of this analysis is to- determine the impact on plant
-Safeguards Systems response if one of the Low Pressure Safety Injection "
(LPSI), High PressureSafetyInjection(HPSI),orContainmentSprar (CS) pumps -has been manually started and is running when a Design Basis Event-(LOCA, MSLB, Loss of Shutdown Cooling, Reactor Trip) occurs which:. ~
h 1.1 Requires automatic Engineered Safeguards Operation with offsite
1.2 Requires the diesel generator to supply power to equipment needed to maintain the reactor in a safe shutdown condition following a Reactor Irip in-conjunction with a Loss of Offsite Power (LOP).
1.3 Require as a minimum one diesel generator to re-establish shutdown cooling (tPSI or CS pump, CCW. pump, raw water pump, air compressor,. and valves as required) in the event of a LOP while the reactor is on shutdown cooling. '
2.0 SCOPE The scope of this analysis is to define the impact of.the manually '
started Low Pressure Safety Injection (LPSI), High Pressure Safety injection (HPSI) or Containment Spray (CS) pump and the associated blocking of the pump motor breakers under voltage (normal loss of voltage or OPLS initiated degrade voltage) load shed breaker trip. .This' includes sequencing impacts. The areas to be assessed are:
2.1 The effect on the successful load sequencing of Safeguards pumps and fans on to the electrical system being supplied by the offsite power or the diesel generator (this is applicable for both safety trains) in response to a DBA (LOCA or MSLB).
2.2 The additional operator actions, if any, required to assure proper Safeguards Systems response to a DBA and the time frame for accomplishing these actions.
L 2.3 The required operator actions to place the plant. in a= safe configuration in the event of a reactor trip and Loss of Offsite Power with no DBA.
r
~
L !
> t s '
EA-FC-90-027 t, .
Rev. O m
Page 13 eaj _
2.4 The required operator actions to re-establish shutdown cooling-following a loss of offsite power and diesel: generator automatic.
start for the cases where either a LPSI or CS pump is used for coolant circulation through the reactor.
2.5 The advisability of a modification which would enable the F undervoltage load shed to operate after a manual start of an LPSI, HPSI or CS pump, and- the need to maintain the original design basis function permitting operator action to attempt pump operation regardless of bus voltage as a last resort measure:due to multiple failures of the electrical system beyond present
[ single failure assumptions. Several options will be assessed.
3.0 INPUTS TO THE ANALYSIS 3.1 OCR FC #9-73 Install Jumpers in Engineered Safeguards Undervoltage Load Shed Circuits 3.2 Surveillance Test ST-SI/CS-1, SI/CS Pumps and valves, Rev 56, 3.3 Operating InstrJCtlon 01-SC-1, Initiation of Shutdown Cooling, Rev. 34, 3.4 Abnormal Operating Procedure A0P-17 Loss of Shutdown Cooling, Rev. 1.
3.5 Operating Instruction 01-SI-1-1, Safety Injection Normal j Operation, Rev. 64.
3.6 Calculation FC 05393, Diesel-Generator Sequential Loading SI/CS i
- Pumps Out of Normal Sequence, Rev. A.
l- 3.7 Calculation FC 04943, Bus 1A3 and Bus 1A4 OPLS Setpoints and FW-6 Starting, j i
3.8 Calculation FC 04315, Diesel Generator Sequential Loading.
3.9 Calibration Procedure SP-CP-08-Devar-TIA4, Rev. O. s 3.10 Surveillance Test ST-ESF-2, Safety Injection Actuation, Rev. 62.
3.11 Drawings Dwo. #/Sht. # Title Rev. #
11045-E-27, Sh. 1 Breaker 1AD1 Schematic Rev. 17 11405-E-27, Sh. 2- Breaker 1AD2 Schematic Rev. 16 161F597, Sh. 9 AI-30A Rev. 7
EA-FC-90-027 Rev. 0 Page 14
- eaj Dwa. #/Sht. # Title Rev. #
161F597, Sh. 5 AI-30A -Rev. 13 161F597, Sh. 4 AI-30A Rev. 13
. 161F597, Sh. 8 AI-30A Rev. 9 161F598, Sh. 9 AI-30B Rev. 7 161F598, Sh. 5 AI-30B Rev. 15 161F598, Sh. 4 AI-30B Rev. 8 161F598, Sh. 8 AI-30B Rev. 8 E-4027 OPLS Voltage Matrix Rev. 7
'11405-E-23 SI-1B Breaker Rev. 13 11405-E-17 SI-1A Breaker Rev. 17 11405-E-13 UV Load Shed Rev. 20 11405-E-142 HPSI Schematic Rev. 13 11405-E-143 CS Schematic Rev. 21 Fig. 8.1.1 Simplified One Line Rev. 45 3.12 Test SP-SI/CS-3 Simultaneous Operation of LPSI and HPSI Pumps on Minimum Recirculation Mode, Rev. O.
3.13 Station Blackout Coping Assessment, Impell Report 01-1390-1763, Rev. O.
4.0 REFERENCES
4.1 Modification MR-FC-88-110, SI-3/A/B/C Start Signal Logic Change, Rev. 1.
4.2 Licensee Event Report (LER) 90-05
i EA-FC-90-027 Rev. O Page 15 eaj 5.0 ASSUMPTIONS 5.1 During power operation, only one LPSI, -HPSI or CS pump is'in operation. This is consistent with the requirement and practice of the Operating Instructions and Surveillance Testing procedures listed in Section 3. One pump is operated at a time for ISI testing, Safety Injection Tank filling,- and verification of operability of a pump due to redundant pump's removal from service for testing or pump failure.
6.0 ANALYSIS 6.1 HPSI, LPSI, and Containment Sorav Pumo Motor Breaker-Interlocks 6.1.1 Each of the SI/CS pump motor breakers is wired such that if the pump is manually started via control switch on AI-30A or Al-308, contacts from the control switchinhibittheundervoltageload shed breaker trip of the running pump. The purpose of this load 1 shed is to permit the resequencing of the CS and SI Pumps on to the diesel generator if initially loaded on the safet to a DBA and subsequent Loss of Offsite Power (Input 1)y buses due 6.1.2 Each of the LPSI Pump Motor Breakers provides a permissive for the : associated diesel generator output. breaker to close and energize the safety related 4160V bus (DG-1-1A3 or DG-2-1A4).
This requires that the associated LPSI Pump Motor Breaker (SI-1A i for DG-1 and SI-1B for DG-2) be open (tripped condition), to permit automatic closure of the diesel generator output breaker.
6.2 Imoact of a CS or S1 Pumo Runnino on Response to a DBA 6.2.1 LPSI Pump Running Due to Manual Start 6.2.1.1 Event -
OBA (LOCA or MSLB)-Offsite Power Available-LPSI Pump !
Running If a DBA were to occur and offsite power remained avail _able, the running LPSI Pump would continue operation while the balance of the Safeguards Loads not already running would sequence on as designed. The . impact on these systems during sequencing would occur at the time the loop injection. valves open and on the first load group. The effect on the loop injection valves would result in slightly lower voltages to the valve motors; this is judged insignificant in that the LPSI Pumps are 4160V motors and have minimal impact on the 480V power distribution level. The 250KVA load of a LPSI pump that is already loaded at 4160V buses 1A3 and' 1A4 load at 10,000 and 14,000KVA respectively is a very small load increase (Input 6). The effect on load group 1 is an improvement in the voltage available to accelerate the motors since there is no requirement to accelerate the LPSI pump.
'.c s
EA-FC-90-027 Rev. O Page 16 eaj.
i The. voltage at the loop injection valves. is expected to be. i' adequate during the first load group in that the transient load is reduced, reducing the voltage transient seen by the valve-motors and contactor controls.
6.2.1.2. Event-DBA - Loss of Offsite Power-LPSI Pump Running ,
If a DBA occurs ' coincident with a loss of offsite power or. l offsite power is lost subsequent to the DBA event the Safeguards .i must be sequenced on the diesel generator. -l The diesel generator breaker associated with the running LPSI l Pump will not automatically close and sequentially load.
Operator action to trip the LPSI pump motor breaker would be ;
required to initiate automatic loading of the. Safeguards loads. .
6.2.2 CS or HPSI Running - Manually Started-0ffsite Power Available )
If a. DBA were to occur while one of the CS or HPSI pumps was- I running, the pump would continue to run while the remaining i Safeguards loads were sequenced on. 4 1
In this analysis the HPSI or CS pump running on a 480V bus during
sequencing has its prime impact on those motors which normally ;
start before the HPSI or CS pump in question and are located on <
the same bus (load center) or bus and tied swing bus and secondarily and on total group acceleration time. The impact on.
motor acceleration time and the total load group start resultant voltage transient on the associated 4160V bus may actuate OPLS. !
If the transient is over 4.75 seconds long and resulting 4160V bus voltage is less than the OPLS set point, an OPLS actuation i
will occur. Input No. 7 curves on page 63 through 68 were used i to determine the impact. For the 4160V -bus heavily loaded t condition the addition of a CS or HPSI pump running due to manual l start leaves little voltage.or time margin. An OPLS trip under these conditions may occur depending on which specific HPSI or CS L pump is running and would be considered a proper plant response.
l The OPLS trip load sheds the-bus and resequences the loads'onto the diesel generator. The effect on other Safeguards Motor Starts by a specific CS or HPSI pump running is discussed on a i pump-by-pump basis as follows.
6.2.2.1 HPSI" Pump SI-2A, Bus 183A, Load Group 1 The effect of this pump which normally starts in the first load group is that the transient is reduced on the first load group because the running current requirement of the motor is much less than the starting current. No impact is expected on tne second load group, beyond what has been already analyzed. No change is i
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EA-FC-90-027
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Rev. 0 Page 17-eaj-expected in loop injection valve performance, the first load group. start transient, which occurs during valve opening, is reduced- in magnitude and the pump running do.es -not have a significant effect on bus ~ voltage, because no other loads on that.
bus are sequenced on.until valve opening is nearly' complete at 8 seconds into the event.
6.2.2.2 HPSI Pump SI-28, Bus 184C, Load Group 1 The bus voltage response to this motor start is expectedito be the same as SI-2A, see section 6.2.2.1.
6.2.2.3 HPSI Pump SI-20, Bus 183A-4A, Load Group 2 The running of SI-2C is expected to have an effect'on the starting time for SI-2A, present worst case starting time is 3.52~
seconds, minimum allcwable time until next load group is 4.15 seconds, OPLS would occur at 4.75 seconds (earliest). If SI-2A-is not fully accelerated by the second load group start, OPLS i would be expected at 4.75 seconds with bus load shedding and ~;
sequential loading of the diesel generator. The loop injection valves are expected- to open if.SI-2A accelerates to full speed.
If not the diesel generator would provide power to open the. ,
valves. The impact on load group 2 if load' group 1 does not r initiate OPLS is . reduced due to the already running SI-2C, no-starting current is required.
6.2.2.4 CS Pump SI-3A, Bus 183C, Load Group 4 The running of SI-3A is expected to have its greatest impact on the starting of AC-3C on bus 183C-4 during the second load "
group. If AC-3C cannot accelerate OPLS will activate, there is little margin available. There are no loop injection valves 'i associated with bus 183C, no.cffect on these valves is expected.
6.2.2.5 CS Pump SI-3B, Bus 1848, Load Group 4 The running of SI-3B is expected to have its greatest impact on the starting time of CH-1C in the third load group. The size of the charging pump is 75 HP and is not expected to affect voltage recovery on bus 1A3, an OPLS actuation is not expected. There are no loop injection valves associated with Dus 1848, 6.2.2.6 CS Pump.SI-3C, Bus 1838-48, Load Group 5 The running SI-3C is expected to have the same effect on CH-1C and the loop injection valves as SI-38. During the starting of SI-3B, the affect of a running SI-3C is to increase acceleration ,
time of SI-3B that may result in a OPLS actuation.
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EA-FC-90-027 E
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F ' Rev. O Page 18 eaj 4
6.2.2.7 Operator Action - Offsite Power Available An assessment of two operator actions is required:-
- a. If an operator desires'to manually trip a running SI Pump ,
or Containment Spray Pump to limit its starting transient '
effect (i.e., prevent possible trip of OPLS), a manual trip i of the pump needs to be accomplished within three seconds of the Safeguard Initiation Signal. All sequencing will be completed- within one minute. -Therefore, Operator action to
_ prevent a possible OPLS trip is not credible,
- b. Due to the limited capacity (600 gpm) of the SI/CS Pump mini recirculation system,- operator action would be required to trip a CS pump if it were the pump running via a manual start and safeguards were initiated. The manual action would. only be required.if there was no LPSI, HPSI, or CS flow,- as could occur under certain-uncontrollad heat extraction events. The present safeguards logic .is designed to start the HPSI and LPSI pumps first and if containment spray is required (spray flow to the headers),
the CS pumps would be sequenced on the bus. In this .
arrangement the 2 LPSI and 3~HPSI pumps require-505 gpm- '
recirculation (LPSI 200 each, HPSI 35 each). A manually ;
started running spray pump would require an additional 200 '
gpm recirculation flow. Under these conditions where there is a 95 gpm excess and an expected balancing of recirculation flow between all six running pumps, some pump heating is expected, however, based on Input 12 which shows no significant heating with 2 LPSI and 3 HPSI pumps running, is judged that adequate time (30 minutes or
~
it more)wouldbeavailabletotriptheCSpump.
6.2.3 CS or HPSI Pump Running.- Loss of Offsite Power If a CS or HPSI pump is manually started the breaker will not- _
trip on Loss of Offsite Power and if Safeguards automatic loading-is required during this time the pump is running (in response to a DBA), the pump motor will be a dead load on the diesel generator. l l
l l
l l
4 EA-FC-90-027
.Rev. 0 Page 19 eaj 6.2.3.1 Effect on Diesel Generator Sequential Loading A calculation was performed to model the diesel generator sequential loading and is listed as Input 6. The results of this. ,
calculation show that the demands on the diesel generator for the altered portion of the sequence are less than that calculated for '
the original plant design, Input 8. The Peak load kilowatts are as follows:
r Peak KW Requirement A Original Revised Per CS or HPSI Desion MR-FC-88-110 Pumo Runnino OG-1 3260* 3028.3 2678.4 l DG-2 3260* 2669.4 2694.8 !
- only one' calculation performed -'
Based on the above information, diesel generator operation is not-expected to be affected.
6.2.3.2 Operator Action 1
No operator action is required to assure diesel generator '
automatic loading with a CS or HPSI pump running.
-6.3 Imoact of an SI Pumo Runnino on Response to a Reactor Trio _ Loss ;
of Offsite Power i
6.3.1 LPSI Pump Running If- a LPSI pump is running-the associated diesel generator would l start but would not automatically re-energize the bus. In this case, operator action is required to trip the LPSI pump so that '
the diesel generator can automatically re-energize the bus. Once this is complete response to a trip will be as directed in the E0Ps. If the redundant diesel generator is operating correctly 4 the tripping of the LPSI pump is not an immediate-priority action. In any event, adequate operator action is possible since the described event is bounded by the Station Blackout Study.
6.3.2 CS or HPSI Pump Running No specific operator response is required, the running pump is a dead load to the diesel generator and is well within the diesel generator capacity, an HPSI or CS pump is approximately 10% of the DG capacity. There are no automatic loads due to a reactor trip except FW-6 which is approximately 10% of the diesel generator capacity. Actions as directed in the E0Ps are considered adequate.
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- EA-FC.90-027 Rev. 0 Page 20 eaj 9
6.4 ImDact of an SI Pump Runnino Durino Shutdown Coolino Response to loss of Offsite Power 6.4.1 LPSI Pump Running - One Diesel Generator Available
-If offsite power were lost the diesel generator associated with the running LPSI pump would automatically start but would not energize the bus. The operator would be required to trip the LPSI Pump then reload the pump after the diesel generator automatically energizes the bus. The operator would then manually start the other plant systems requ Ned to maintain shutdown cooling. This is, in fact, what occurred on 2/26/90 as described byLER90-06(Reference 4.2). The operator tripped the LPSI pump breaker and re-energized the bus via the DG within 44 secorids of loss of offsite power.
6.4.2 CS Pump Running - One Diesel Generator Available If the offsite power were lost the diesel generator would automatically start and re-energize the bus picking up the CS pump as a dead load. The operator would then manually start the other plant systems required to maintain shutdown cooling.
6.5 Identified Deficiencies and Corrective Actions 6.5.1 Design Dc?iciencies The following deficiency has been identified in the analysis to this point:
Diesei Bresker auto closure is blocked when a LPSI pump is manually started and running at the time offsite power is lost.
6.5.2 Possible Corrective Actions !
6.5.2.1 Delete LPSI Breaker - Diesel Breaker Interlock The diesel generator breaker close permissive (see Section 6.1.2) could be deleted. The running LPSI pump is of such a size that it can be picked up as a dead load, with no effect on the.
generator sequential loading. D2ference 6, Calculation FC-05393, demonstrates that diesel generater loading will not be affected.
Therefore, the original justification for this design feature has been shown to be invalid and there is no negative impact from its deletion.
4
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e EA-FC-90-027 Rev. O Page 21 eaj 6.5.2.2 Delete Manual Start Override of Undervoltage Load Shed All CS and SI pump controls could be altered to trip on undervoltage load shed no matter how the pump is started. This could be done with a jumper in the control circuit to defeat the control switch block of load shed. The negative effect of this design change is that an operator would no longer have the ability to attempt a manual startup of any of these pumps during a post-accident, undervolta condition. However, this ability is likely not useful anyway,gesince a motor requires 90% or better.
of rated voltage to successfully start, As an alternative, a bypass switch could be added to enable load shed at all times during normal operation or placed in bypass to permit the operator to close the breaker regardless of bus voltage condition. Deletion of the diesel generator breaker auto close permissive of the LPSI Pumps would'not be necessary in this case. Please note that Human Factor considerations-indicate that all 8 SI and CS pumps should operate the same way.
7.0 CONCLUSION
The permissive 3 or interlock 3between LPSI pump breaker and DG breaker closure should be deleted (CorrectiveAction6.5.2.1). This eliminates the possibility of not having a diesel generator automatically load in-the event of a DBA and Loss of Offsite Power. This would result in a very small increase in the probability of an OPLS actuation in the event of a DBA. There is little margin between the-trip setpoints and expected bus voltaget Jnder low offsite power voltage conditions. The effect of an SI or CS pump running is approximately an additional 250KW in the first load groups with approximately 10,000KW on bus 1A3 and 14,000KW on bus IA4, which is a very small change. The OPLS would be functioning as designed under these conditions. Physically, this design change has very minor impact as it involves the jumpering of two contacts in the Control Room.
8.0 ATTACHMENTS Title Number of Paoes
- 1. DCR 9-73 43 i
- 2. ST-SI/CS-1, Rev. 56 39 ;
- 3. 01-SC-1, Rev. 34 7 I 4 A0P-19, Rev. 1 i 23 .l
- 5. 01-51-1, Rev. 64 32 !
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EA-FC-90-027
[b Rev. 0 .
Page 22' eaj i
- t. ,
'i
.- J,j,1],1 Number of Paaes- ;
o-
- 6. . Calculation FC 5393, Rev.'A 17 .l
- p. ~7.- Calculation FC 4943, Rev. 0 106' '
t
- 8. Calibration SP-CP-08-Devar TIA4 .Rev. O. 5 ?
g 9. ST-ESF-2, Rev. 62' 25 i
- 10. SP SI/CS-3, Rev. 0 23 !
- 11. ' Station Blackout Report, Rev. 0 - 67 't t
- 12. MR-FC-88-110, Rev._1 4 j, s
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