|
---|
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
. 1
~ '
n a n. -
-9 e - -
w g __
Omaha Public Power District 1623 Harney Omaha, Nebraska 62102 402/536 4000 December 19, 1983 L IC-83-305 Mr. James R. Miller, Chief U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C. 20555
Reference:
Docket No. 50-285
Dear Mr. Miller:
Adequacy of Station Electrical Distribution System Voltages at the Fort Calhoun Station Unit No.1 The Commission's letter to the Omaha Public Power District dated October 20, 1983, formalized the latest request for additional information on the sub-ject issue. The following responses are labeled by the number of the re-quest.
- 1. The attached two tables ( Attachments 1 and 2) together with the fol-lowing discussion provide the District's response to the first request for additional infonnation.
The two tables contain analyzed voltage values which have been revised using more realistic loading rather than the more conservative loading which has been used in earlier analyses. These loading figures are based on a load survey which was conducted this past year (see Attach-ment 3) and also on the manufacturer's specifications of pump loading requirements under various operating conditions (see Attachment 4).
Specifically, the condensate and feedwater pumps which when operating m in the recirculating mode, as they would be during accident conei-tions, require 70% and 63% of their motor horsepower, respectively.
So Also, there is an automatic 480V load shed initiated by the accideet no signal which was not taken into consideration by previous District
- analyses. Thus, the maxinum post accident loading on either of the o
O safeguards buses would be 9.82 MW on the 1A4 side, (tte 1A3 side han only 1/3 of the condensate system, thus it will always be more lignaly gg om loaded than the 1A4 side which feeds the other 2/3, therefore, volt -
7 ages were not analyzed for the 1A3 side). The 9.82 MW includes bus y 1A2 and all loads which could be, but would not likely be, running, i .e. , worst case.
me.c.
The minimum and maximum grid voltage values are detennined by the Sys-tem Operations Deoartment 9perating Guide 11-78 (Attachment 5). This 4sse4
/ p) cmpioymeghfauagopponumty f
. - - .. -- -. = - - _ - _ . - . _ - - . _ - - . _ - -
December 19, 1983 Mr. James R. Miller Page Two i requires that operators maintain the 161 kV level at the Fort Calhoun
- - substation between 163 kV (101%) and 169 kV (105%) and the 345 kV at a minimum 351 kV with the unit out of service. As discussed in the Dis-trict's original design (see Attachment #6 of the August 28, 1978, sub-4 mittal) the gener.stor actually regulates the voltage on the 22 kV bus when it is operating in a preset range regardless of what level the
. offsite grid is at. To illustrate this point, a recent check with the unit at full load showed the 345 kV at 103% and bus 1A1 at 99% of 4160
- v. Because the unit does regulate the 22 kV bus, calculations were i
! not done for the case where an automatic fast transfer had occurred ;
switching buses 1A3 and 1A4 from the preferred 161 kV to the 345 kV i with the unit remaining at 100% load. However, the hot shutdown oper-ating mode would be the loading condition relevant to lower voltage on
-the 345 kV grid. This loading on the 1A4 side would be 7.14 MW, in-cluding one each: feedwater pump, condensate pump, and heater drain i pump. Operation with buses IA3 and 1A4 on the 345/22 kV system with the unit at power is done only on very rare occasions, however, the
- District will take steps, via operating procedure, to assure that the i bus voltage does not exceed 4400 volts (110% of 4000 volt rated motors) . This will be satisfactory; the plant does have direct con-trol of the 22 kV bus voltage via the generator exciter control.
Also, in order to substantiate these maintained values, the actual 161 kV and 345 kV levels have been recorded beginning September 30, 1983, i to the present at approximately 8-hour intervals. The lowest recorded
{ voltages have been 164.3 kV and 347.0 kV (102.0% and 100.6%, respect-
- ively) and the highest voltages were 170.9 kV and 358.8 kV (106.2% and ;
104%, respectively), while the average values were approximately 168 kV and 352 kV. These minimum and maximum grid values are well within the safe operating range for the Class 1E motors at the Fort Calhoun I-Station which is guaranteed by motor manufacturers to be 90 to 110% of
- nameplate voltage. As shown in Attachment 1, the minimum analyzed grid voltage of 101.1% of 161 kV provides 96.6% of nameplate voltage (460V) at the motor teminals (worst case). This 101.1% of 161 kV is i the analyzed minimum expected grid voltage (ref.: the District submit-l tal of August 30, 1983), while the minimum allowable ac per Operating l
Guide 11-78 is actually slightly higher at 163 kV or 101.2% (see Attachment 5).
! Calculations were not done for the steady-state maximum case simply be-
- cause it was obvious that the maximum expected 161 kV grid level would
, have to be in the range of 113 to 114% to cause a 110% motor tenninal voltage, and the maximum voltage analyzed on the grid is only 105.1%,
while the maximum recorded is only 106.2%. The maximum analyzed is lower than the maximum recorded for the same reason that the minimum analyzed is lower than the minimum recorded; because the voltage drop i parameters used in the calculations are worst case and thus more con-servative than the real world operating conditions. This consistency points out the validity of the model used for calculating the grid voltages, i.e., the analyzed values are consistently in the range of
- 1% lower at both extremes, both minimum and maximum.
The minimum transient voltage values, as per the subject telephone con-ferences of September 26, 29 and October 6,1983, were to be calcu-
_ , - - ~ - . _
.,_v~-__.,.__ , _ . _ . , _ . - . . _ . , _ . _ _ . _ ~ , . . _ . _ - . _ ~ . . _ _ _ _ . _ _ . _ _ . . . . . . . _
Mr. James R. Miller December 19, 1983 Page Three lated based on the inadvertent starting of a large non-Class 1E load during. accident conditions to detennine if it would actuate the acci-dent undervoltage (0.P.L.S.) relays, thereby automatically transfer-ring the Class 1E buses to diesel-generator supply. The analysis determined that the starting of either a reactor coolant pump or a feedwater pump (both highly improbable occurrences during an accident) would cause a transient both low enough (83% voltage) and long enough (15 sec. in the case of the reactor coolant pump) to actuate the 0.P.L.S. relays. The 0.P.L.S. relay trip setpoint on bus 1A4 is 89.97% voltage for 5 seconds. At the end of the 15 second motor start transient (RC-3D) the bus voltage would recover to 93.4% and the 0.P.L.S. relays would reset at 90.9%, according to the manufacturer's specifications, allowing the transfer back to the 161 kV grid.
- 2. In the District's submittal of August 31, 1981, the results of some transient starting tests were compared to the corresponding analyti-cally derived values. The District believes that this comparison showed the validity of the analytical model that has been used consis-tently since the original undervoltage study submitted on August 28, 1978. The important parameter to compare is the consistency of the difference between the calculated values and the tested values, and as discussed in the August 31, 1981, submittal this difference was consis-tent. The magnitude of this difference is a function of the selection of the input parameters and thus is not as important. For example, the conservative bus loading values used in the calculations of the August 28, 1978, submittal and all other earlier submittals, accounted for a comparative difference as large as 3.8%, however, the consisten-cy of this difference varied by only 0.3%, down to 3.5%. Therefore, the actual voltage drop model is accurate and the District does not believe that any further testing is necessary.
- 3. The taps on transformers TIA-3 and T1A-4 are on 161 kV and this is what has been used in the analysis.
- 4. See Question #1, and Attachments #1 and #2.
In closing, the following list of District submittals to the Commission is provided so that the Commission may verify that they are all available for reference in the Commission's file on the adequacy of Fort Calhoun Station distribution system voltages. It has been brought to the District's atten-tion in correspndence over the last 3 or 4 Commission requests for addition-al information, that due to personnel changes the Commission may not have reviewed past infonnation which has been provided by the District. If any
.of these submittals are not in the Commission's files, the Commission is requested to notify the District so that copies may be sent.
- 1. September 17, 1976, to George E. Lear, ONRR
- 2. August 28, 1978, to Robert W. Reid, ONRR via H. H. Voigt of LeBoef, Lanh, Leiby and MacRae
- 3. May 13, 1981, to Robert A. Clark, ONRR
- 4. March 19, 1982, to Robert A. Clark, ONRR
i I
Mr. James R. Miller December 19, 1983
, Page Four
- 5. May 21, 1982, to Robert A. Clark, ONRR
- 6. Decenber 1, 1982, to Robert A. Clark, ONRR
- 7. April 22,1983, to R. A. Clark, ONRR
- 8. August 30, 1983, to R. A. Clark, ONRR Sincerely,
,, r' 4 W. C. Jon,es Divisio'n} Manager Product' ion Operations g 'JCJ/0JM/rh-A Attachments cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
4 Washington, D.C. 20036 Mr. E. G. Tourigny, NRC Project Manager Mr. L. A. Yandell, Senior NRC Resident Inspector J
5 4
9 Attachment 1 Worst Case Analyzed Voltages With the Plant Distribution System Supplied by the 161 kV Grid Plant Conditions: Normal Operation Plant Conditions: Post Accident Operation, All Class 1E Loads Operating With Unit at 1005 Load Transient Minimum Steady-State Minimum After Steady-State Steady-State Large Motor Start Transient Minimum Due to Large Motor Start Maximum Offsite See Note See Note 105.1 101.1 Grid
(% of 161 kV) 83 93.4 96.2 (90.9% is required for reset Bus IA4 (Start RC-3D with
(% of 4160v) See Note (9.25 MW Load on Bus) 7.82 MW Load on Bus) of undervoltage relays) 96.0 93.3 Terminals of (AC-108) See Note Class IE Load See Note
(% of 4160v)
Bus 184A See Note 90.4 See Note 93.1
(% of 480v) 93.8 Terminals of 96.6 See Note Class IE Load See Note (AC-3B)
(% of 460v name-plate voltage l rating)
NOTE:
See the discussion of the applicable question for explanation of why these calculations were not perfome
Attachment 2 Worst Case Analyzed Voltages With the Plant Distribution System Supplied by the 345 kV Grid Plant Conditions: Normal Operation Plant Conditions: Post Accident Operation, With Unit at 100% toad All Class 1E Loads Operating Steady-State Steady-State Transient Minimum Steady-State Minimua After Maximum Minimum Due to Large Motor Start Large Motor Start Transient (Observed) (Observed) l Offsite Grid 104 100.6 See Note See Note (3 of 345 kV)
Bus IA4 85.9
(% of 4160v) See Note See Note (Start RC-30 with 92.8 7.14 MW Load on Bus)
Terminals of Class 1E Load See Hote See Note See Hote 92.7
(% of 4160v)
Bus 184A
(% of 480v) See Note See Note See Note 91.4 Tenninals of Class 1E Load See Note See Note See Note 94 .8 (S of 460v name-plate voltage rating i NOTE: See the discussion of the applicable question for explanation of why these calculations were not performed.
I
Attachment 3 Load Survey Assume TIA1 Feeding Bus 1A1 T1A2 Feeding Bus 1A2 TIA3 Feeding Bus 1A3 TIA4 Feeding Bus 1A4 Alignment 1 is considered worst case loading on the 161 KV systen. T1A2 is shown at its lightest loading.
Alignment 2 is the Itghtest loading on the 161 KV system.
Alignments 1 and 2 are given assuming all equipment is running necessary for 100% power operation of the generator.
Actual data taken with the unit at 100% load on February 4,1982, at 0830.
Bus 1A1 7.5 MW RC-3 A, FW-2A, FW-14A, CW-1 A Bus 1A2 6.5 MW RC-38, FW-48, FW-58, CW-1B Bus 1A3 3.3 MW RC-3C, Misc. Loads Bus 1A4 6.2 MW RC-3D, FW-2C, FW-5C, CW-1C Alignment 1 Bus Ma,ior Loads 1Al RC-3A - 2 MW FW-2A - 1.62 MW FW-4A - 2.84 MW FW-5A .49 MW CW-1A - 1 MW 1A2 RC 2MW FW-2B - 0 FW-4B - 0 FW-5B - 0 CW-1B - 1 MW 1A3 RC-3C - 2 MW Mi sc . - 1.3 MW 1A4 RC-3D - 2 MW FW-2C - 1.62 MW FW-4C - 2.84 MW FW-5C .49 MW CW-1C - 1 MW Mi sc . - 1.3 MW
- _- .o
. . - .. . . . - - = - - . _ - _ - . . - - - . . . . . . . - - - _ _ .
Alignment 2 Bus Ma.ior Loads ;
1A1 RC-3A - 2 MW FW-2A - 1.62 MW FW-4A - 2.84 MW FW-SA .49 MW '
CW-1A - 1 MW 1A2 RC-3B - 2MW !
FW-2B - 1,62 MW FW-4B - 2.84 MW FW-5B .49 MW CW-1B - 1 MW 1A3 RC-3C - 2 MW Mi sc . - 1.3 MW 1A4 RC 2 MW FW-2C - 0 1
FW-4C - 0 FW-SC - 0 CW-1C - 1 MW Mi sc . - 1.3 MW i
A -rt ae.h me.n t +
(
Desian Parameters Items number CW-1A, CW-1B, CW-1C Number 3 Type Foster Wheeler 84" MFV-2 K6.6 Design capacity, each 120,000 gpm Total dynamic head 33 feet Operating temperature 85'F Pump Efficiency ,
86.57,as shown in Figure 2.1.2 Materials of construction Casing Cast Iron Impeller Ni-Al Bronze Shaft Carbon steel Hy-Ten B-3X Annealed Steel Pump Speed 295 rpm Drive Electric Motor 4160 V 3 Ph ase 60 cycle Design hp 1175 = o.88 ^'1 W Flow requirements Condensing water 315,000 gpm (design flow @ 60*F)
Bearing cooling, (2) 17,900 condensate cooling Screen wash 3,000 Surface diversion 24,100 360,000 L
4
r' III-3-13 .+
2.0 SYSTEM COMPONENTS (Continued) 2.3 Condensate Pumos (W-2A. W-23. and W-2C) 2.3.1 General Description The condensate pumps are vertically mounted 10-stage motor driven turbine pumps. They consist of two sections, each of which contains five stages. The
- sections are coupled together to form one unit.
Condensate is supplied to the pump through a suctior '
strainer. The condensate flows down the casing to the bottom where the pump first stage takes a suction and discharges to the next stage bolted on top of it. Eac.2 stage discharges to the next stage, increasing the pressure of the condensate as it progresses. The pump casing.
is equipped with a continuous vent connection that r e ren any noncondensable gases and vents them to the conde .
The pump shaft is sealed by a rotating mechanical se which is filled and flushed prior to startup and the cooled and lubricated by water from the discharge of ..r.
pump through valve PCV-1214 when the pump is running. '.a i.a pump is capable of supplying 50 percent of the required condensate flow for 100 percent teactor power.
)
2.3.2 Desien Parameters g w
( Item Numbers W-2A, 23, 2C
. Number 3 Type Vertical, Turbine Shaft Seals Mechanical Power Supply W-2A Bus IAl W-23 Bus IA2 W-2C . Bus 1A4 Design capacity, each 5600 gpo Total Dynamic Head 1150 Ft.
Operating Temperature 92*F.
Operating Flow at 100 percent load 4600 gpm d88 BED MAY 5 1981 t
^'
, .. 11I-3-14 2.0 SYSTEM COMPONENTS (Continued) 2.3.2 Design Parameters (Continued)
(
Materials of Construction Outer Casing '
Welded Steel Impellers S.S., 11.5-13 percent Chrome, 0.5 percent moly Shaft S.S., 11.5-13 percent Chrome, heat treated
' Pump NPSH Required at Design Flow 0 ft. @ base Pump Speed 1190 rpm Drive , 2000 hp Electric Motor 4160V, 3 Phase, 60 Cycle Pump Horsepower at Design Conditions 2000 hp 2.3.3 Instrumentation and Control The condensate pumps are controlled from two locations, k one is the main control room on C3-10 and the other is locally at the pumps. Local control consists of push-bucton start and stop switches. They are mounted on the west wall near the pumps. Remote control is ac-complished,in the main control room on Panel CB-10.
Three swittnes control the condensate pumps. Also located on C3-10 are green stop/ red run lights and an ammeter for esch condeosate pug .
To start a condensate pump, the breaker must be racked in and the "69" permissive switch on the breaker cabinet must be in reset. The Auto /Off-Auto switch in the control room must be in Off-Auto. khen these conditions are met the pump is elect.tically ready to be started.
After a condensate pump is running, the operational control of the pumps can be placed in an automatic standby mode.
The Auto /0ff-Auto switch is coc: mon to all three condensate pumps as well as all feed pumps, heatsr drain pumps and the motor driven auxiliary feed pump. klen in Auto, this switch, along with the position of the individual conden-sate pump contn l switches on CB-10, set up an automatic control circuit for the standby condensate pump. The 1
Il s 4a R2 5-5-81 (
maiW MAY5 1981 i \
~
4 4
'I '
.. :. n.._1' _ b: .
- I :i.
_..:. a.a. .
IfjN dcf*k.].
.& :.;... 4. 4... Gh. 6 R +4 5M -4aC 3: .!}f' R?.
ih*;4 R: *iff!' GUS4. . . . if;i La W':P 1i
.F k
. lb g l! i
.! !if ST
..~.F._.,f;.s*. r" ' .': .
. .. : ..t 1- c. _
+: * :
.. ....... . '...~.-
7
'. y I.y;; . -.- . : 'l' :k
....:TW ib.: . . b.
- 4. .~ , .
--. 7 - ---
. . ..... . bt....C. " . . .'I,
-+++~..
/if ' li: :! : !- K 3W MIF i [ Q ,jh. T."ij:p~ -[ ,o p t{
- y A. ~..] 0 r . -
i jfsw..r n : Lp _.... .. : ' '.
..... .i- ..: . ~ ,. .L . ...:
i 7 .
.! '.i'
..,.=..l 3, N,0
.:. . . c. . . .7 .. . ..h:.:.:
l .'f k. i :. ,
.;- .f- .l l- I .,i .__.h;g . : 1.
[ 1
- M i ~;
).
- .}' -
. :il!: .;. ' h[/ l-
'f .ii f ' f ! a. . ' ! E' !![ g (g)
.% .i-i.
,..g-..-~. . j .. .... .
. .l '-. ~ t- . J j . . jul.a.l!% . *
f' . .. . 4 ... j . )%gr {Ruo . ' *, , f,,
i::
- [
- ~l'
. . Q l';*Q
- l
- t: j' : ! :. .
... @n Q
.' . r - - %:
--i" - - j,!"
h.1 i"-- ~ ii-- U:9 m *g..O #~" C '- 3[' rl..;
2 d. ... M'
" 3
.t. ..:
uj...o. . . : .
- .:." c. . ,'- d. . . If". . . ---
r-
; .. ..l... u. : :l:
.. :l.:'
- l. r a. L. a. . -*: 2@.+' .
- n. . ~
- : i .
T i
g .. ,- .. . . . . . .. .... .. % a
. .t. .. . '.
t . .'::
- t.. :
- ::h-
,. ....... 1
%.4
.!:. : !. :. : 11 5- :.
- J. +.:: '!y . . * . e .
+
- 7. , - - - . .., e J .. -
- [ . [" :5..bi i !
. ifh
- ;)'j: . : ':
.;. : ". :--l: - '.
i -..C Q1.
4 :. . : : i *i.
M .u...jMhh4..
; .; p ; i c{: i;': _..?': ::
!ili L{'
g.in{ . 4{H{i._. au.!.{ !p.... .k t A ;
I.
ilii{iif! ;
n: : : *
..'. f. .' - ,I I . ' l ' ..r. t.: . i. ' ' *
. ' . ' '- - -- g p d l "
. {.
'.. . . :. .g. 3
- t. .
- .i. . . . ::: ;: .,..
.". :. . .::: . r u . : I".-
.l
....t:
l
+
i . ..-
;*~*
-.. . I:
. :n:z;.n.ti:t..mn,a a.
. ~
fr..:;'T* p} % - N.. . " .i. . ;; .
- ~ ~~ty* ~ .m . ' r- o ,
ehi:.. : [. :.ir. d.. d..
- t. - f ::*:l.. *::. .n.. .. '":.:, :.h. r ..: .4. :.... ! - r *:
c'
- }:. . .-n ..$... '*-".: ... nn
... ..t!-*** :"X:.:1,%;. ~ =,
#~
m d...
... . . , . . . . ...m.. *g.. .v
.. g: . .ptr:a I. !. ..w
... *M..."*
. *t:'. . .
;1
. w- *: .{:.*:.
- gn. m%g3.i.h-
..n u: c. .. . . g" :f 6n;,.n:!.g.:,h..p:'..
.. *:u ...In. : "
m ng ;,. g g;n .".
.. , s
- - b g
% . ;41fg::
n{:. , :f!:ni:: @:"":Q:: f::; f: k . .: M4,N. p.g
. !: ':: . ..n f':. ,
- l::..::::-*::$ . tim.;; m g. : . ~.
- ;!: * . 11 r"- n:ji;r':{:.,
1., . h :. : -
4'hT:C M'** 3 : . :
c
...j: t M "N: y T:" JQ* .]:V:i G. ". . :] @:: - j g
. [" :: . - tJ:.t : :.
;; *g :
'* qaig; [
F -
-- M. ; ~ m. :.-Q: :*l O . . : . ttt Z .,
y
- m. i. :.":a. .- u. .. . . 3. g. . A l f. ... . . 9 ..z r, .p:.tr. 2: *: r.$. _ ._r.
2
- (,
.: r. . t. .
.7. . . . . : n9.t :. ... a. :
2.nih_r.].g
- n. . .
. u .
, . . . l. . : 1. ..
.MiAU 9.h.i..LM..~ ii C,
-y : ;;;M ~ g ;;;.M. . fih. i!.I.'.l.i.,!! :'id},N,q.: l.i.g
. t. : . * *:. p. . . . j'.1. : . .g . . ::l3.. i. . . . . . .
"L* *-*n
,Mr ::*J 1:=
- E : t*j:! -{: - . ' ' ' " b"""II;*g; ;;,,
... ;.M n* * *
- l. : : ~!!: "
- . :n . . :
- ":; ' :.J f;**r.: y ! :L, 6 o...
-g
!!'.(t : C : "{*" ,g: .t .y.gg {
,t W:: Pr.U '!**" lw "f1".}'ti!- M i .: :. . . * . ::;;::ni;;'
- O ,
- h . - ,p'[
{ : . . :. . .:: l . :::!: ... .. . . . . :l. . !T r i t* :" t %;:
;".;:}; :u ;2{ ::t. ty.; ::.ipt T, ii: ':
. :!: . .. - W :.:::;n. ;
- i
.:[f: .-
;n 7:
. . .
- r :r:r: (/)
.._1.. . . T rm ~
. N. .
r- t-"- - - --
p p-j- +
- 1. . . ;b.i . . f"'
f "$*l %
. m.I ,st- ~l :!* r=
] <!
- r. q:.. - :t:
.f. . . . ,,... .. .
. . . . - . . .!..:: :. 9 :...1"
.t. .... ., c- -
- [r--29 m.
.e , .. .
- i. - : *! : - .: u..: L. . p.,. . :.t. *: i::
....i4 V . i::
. i. :. ' " ~ ~ - g . ' r. i. N;t.: tp
_;;u.;
- {.::. .J:.
-.7,._.. . ....
; v q . .-
4,;;;,. .; .uu.
;uzup: y t - - ::: ....- -. : ~; .;: k i :-
.m-1 .. . ::f
. ,j , ; : , , - f' . - ! 9: , d. fys.;
s j .g ,
m :n- p - p :--g u em
.! g. ,;.g{.. .: . ... .. .,. ,
-. - p :. --:;- . . . . .:-
W.i J,-- .
- -- . . . o -q: , . .r-....r . .: .. ..... -
- - . - . . . .-.- 1 .: ...-;.. .i a:
w ...m.---
- Cts " F(- M
...T wim F -
- t y- m s i '*a.
s@t,M
. .. m
- ..
.q" l u.nc uk' ... .u. l . ..nu.. {
; t! $ ,I I
.._._ p.,,._'!_
I 7... _'...' .' kc4" Mg_; 4 a _ _,, q ;((_;{ Q',._ g .S
'O
'l.' . I .! 1[ .-.' ['_ .y . .7
.1:
. ';n b--
Cr-". :--]---- - t 25 ' !
; . S. -
. .? 7
- l. . ;
.....;_.. .._ J n;
, :c j._ ,;,. m -- 7, .
.. e. q .c ,
1 .I . , . .
I
, {, , b d
.l . .r~ w% - .,
n ' .Q .} I 9 n ..A;
.l.Lg
~~
^
5
- j i. i - :k_ L : .-
y;'
...._...:j ;%- U
.,l
; .1
; }
;Q, ,.
.{. .I. ,. . , , .
s(. - ._. J! A e g f
',./. ..L.
- l. t - ,_
--. . .. 7 . .- .._u 2
, _ f__._ m r g ^
.t .
t
,,_ _ ;_ , x]: { , .
a, G +J ;
w;E '
<j - N j - .f 1
- 4 -
i N .A .,
> u, ! x(- '
~
r4'S
,O{e
, . s t
" * ~
[
' \,,
m
. ~ . . . $ e- i s.4 y
....______._;.L.,,______,__j y ql3f~ g a
i -4 .
3
- Q (3 n p F1 3
7 "b.n c1 ; 1 '! q"
'k. ~
- A yJ & .
n 3.. .
. . . w . . *
. .i L 4 m ;
i ,
},
! j L ,.4.N! N H 17 i C f. .
~.._ ._ _.
'h i I.p.
L *
._ _ _ _ _ _ _ __ _ . _ n. . ,
w ~
J .
III-3-32 2.0 SYSTEM COMPONENTS (Continued) 2.10 Steam Generator Feed Pumus - W-4A. W-4B. and W-4C L
2.10.1 General Description h
. . ^-
The steam generator feed pumps are horizontally mounted two-stage motor driven centrifugal pumps. The pumps function to supply feedwater to the Steam Generators.
Each feed pump has a separate oil system that lubricates the one thrust and three journal bearings. The oil system consists of a sump, auxiliary motor driven gear pump, a gear pump connected to the feed pump shaft, cooler and interconnecting piping. During normal opera-tion the gear pump connected to the feed pump shaft supplies oil to the system. The motor driven auxiliary gear pump is intended for use during startup and shut-down of the feed pump. In the event of trouble with the shaf t driven gear pump the auxiliary gear pump can and will supply the feed pump with oil until it is stopped.
Each feed pump has two rotating mechanical seals, one on each shaft end as it penetrates the pump casing.
The seals are initially filled with water from the condensate system. They are then kept full and lubri-cated 'Jy pump leakage to the seals and the pumping groves on the rotating face circulating seal water through the seal water cooler. (
' Each feed pump is provided with a suction relief valve to protect its suction piping from overpressurization in the event of back flow through the pump when it is stopped.
Each pump is designed to supply 50 percent of the required feed flow for 100 peret:nt reactor power.
2.10.2 Desien Parameters Motors 3 Allis-Chalmers 4160 Volts - 3 phase - 60 hert:
Size 3500 H.P.
Speed 3570 RPM Power Supply W-4A Bus 1A1 W-4B Bus 1A2 W-4C Bus IA4 3i 9
/5C '
k hlI R2 5-5-31 MAY 5 1981
III-3-33 2.0 SYSTF.M COMPONENTS (Continued)
{ 2.10.2 Design Parameters (Continued)
Pumns 3 Byron Jackson Type Centrifugal, horizontal Shaft Seals ,,
Mechanical Total Dynamic Head 1740 ft. (full flow)
Design Temperature 396*F.
Operating Pressure 1090 psig Operating Temperature 396*F.
Recire. Flow Rate per Pump 750 gpm <= Co,-r e s eand s +o a 18 c o H.P l encJ Pump Discharge Pressure at Recirculation 1560 psig f .p, o m puma
\ c w-ve. J Design Flow (each pump) 8000 gpm N.P.S.H. @ 100%. Load 133 ft.
N.P.S.H. @ Design Flow 143 ft.
Flow Dats @ 100% Load Feedwater Flow 15,200 gpm Nominal Operating Press. 1055 psig Final Feedwater Temperature 437.9*F.
Blowdown Rate 2 percent 2.10.3 Instrumentation and Control The steam generator feed pumps are controlled from two locations, one is the main control room and the other is locally at the pump. Local control is performed on a control box for each pump mounted on the north wall directly adjacent to the pump. Each control panel consists of three sets of pushbuttons with associated lights. The pushbuttons control starting and stopping the feed pump and motor driven auxiliary oil pump and opening and closing the feed pump discharge valve.
Remote control is performed via switches located on the desk section of C3-10. Three switches control the feed jQ i
g1 p pumps and three control the motor driven auxiliary oil I 2f .S 5 r
Pumps.
i uf- Q *<
- J.2 5-5-31 MAY 5 1981
i i LN33lH3 d-ADN313fd.-El : ;
. i.
.8.2 .R.E S 1 8 8 2 i .
. ;y n '
s
. : d H 3 )lVd8 4 .
. =-- . . .
.. _ ' .. . . s 5 ... .....g..,. . . .g: ,, ,4 hM g
! ! $ (z, t i !
l . LL. . . .
I ; '
I.
. .. l
) h j
- o
;m
.._.. ..M
. . . R I
i i . .i.: . . . ,i . . . . NY M
. } :
3 . . ,
..p . -
- )
Q -
p
- ~ . .
.- .. ~
. ... .i. :
. : 2q i
I 2 %
- l Z_%.. .' !
t I
I :
-t O : : '
m.
y) x 's '
.';..".((......
,.Av
. s
. l
- i. " i ' ~
? >- j .
C
. ..:: .j.. _ .k.. !N g
- .. . rg .t....:.
. .. t . .. . . . :[. . !j[ _' .: ..
4 . . ' .I . .i ..
- k. . :: : . . .:.... . ..li
- 2 ' -
~1 M.\ '. . .I . . -
.b..!..'.. : :
i Sik.f..!. ii c ,
s.
l . .k YI -
[ .. i ..k .i. . .; . :. ..
l...{..
.e :
.g .. . : :
...o....-..... s..
O ri i g-4
. : V ,
i.
!si aR W- <
tt- : :
,i . . . .
.. 2 :
- . :g 3
5
-- t--
N n
< ?
. m.
. 3 0
'..;. e -
i >
.g. ..
g .. . . < .s
[. . l
. N . . . . . . . . . .....k.. ..h....: .... . ..... .!........ . ....;..
j 4.t :
l .. l. .
i ,t. 2 M,. t *'~~ gl 1
- g .
' : I Q
l i
, .jf j
%~1 s fi--t f, M 3 l-[.; p.
l
,: _3 i
...,....g....... ...:
i
. s. g i . o <
-4 yg i . .
- .m .g ..
t v .,
. 't. -
g.g...........,-......._.._x . . _ _
_ __ _ .._,_..._...L.__.....
- Oc .
1 t,3 _p'
- h. . C;
,s. $1- ..
, N, E e .,
.c.*
f N Mi N. . .N
' g .
s
' d.N 1 l
; i pf
! \
l, . n.. : . _ , . . . . .
\*
I * ,1
. s i e . ./
nn .< tv . :in w u n : G L
- x.
_9 I. ..
L
. . AttaeI,nac.nt 5 SYSTD1 OPERATIONS DEPARTIEIT _
c OPERATING GUIDE 11-78
Subject:
Operatine Voltace at Substation 1251/3h51 (Fort Calhoun)
Reference:
D. D. Wittke -(P. K. Mazumder) letter GSE-FCI-78-390 of October 20, 1978, to System Operations Letter Text:
Subject:
Operating Voltage at Substation 1251 and 3h51 As requested by you, following are the liraiting operating voltages at Substation 1251 and 3h51:
Substation 1251 Minimum allowable voltage: 163 KV Maximum allowable voltage: 169 Kv Substation 3h51 111nimum allowable voltage with the unit out: 351 Kv This is for your information and necessary action. If you need any further clarification, contact P. K. Mazumder (h590).
Action for System Onerator: Maintain voltages within above limits.
i f
R. E. Taylor Supervicor - System Operations RET /jmm 10/30/78 I
1
f *' O D OP A16-1 Port Callioun Station Unit lio.1 Operating Procedure flo. 10 Ananunciator A-16 I '
f CB-20 Panel ,
4 < s
.lAN 18 Jg79 l
l
.= .. _
l Yrunu TIA- rruns TIA-L Trans TIA-1 14160 Volt l Oil Level
[ Secondary jl:160V llun Hus Trans la Gil Iow Voltagt / Ground to 22KV Teinp y lilocked 3 A-1 _ MM A-1 A-h A-5 _ f. _6 Trans TIA-1 Unit to 1:160 V Bus h160V Bus h160V Bua o tii ndi rig llouse 1 A1 Iov 1 Al-1 A3 125 1 Al-1 A3 125 3-Teing 111 Trans fer Voltage V DC Trans- V DC Trans-Pural 1 el rer Switch rer Su.
O Orr flormal Emerg.
Supply Orr 3 141 B-2 11-3 B-b B-S trormal it .6 4 h80V Bus 180V Bus Trans TIA- Trtuis TI A-i likr. lAll Bhr. l A13 4 l'res sure Gas Press. Auto Trip Auto TrlP 1B3A/.1B3A-1113A/1B3A- p 1(elay Oper Itel l t. r hA/1B3D/ f$f3c_
h3k,fUh , hC 125 VDC
.Trans Sv.
C-1 C-? c-1 c-h h$0N1 0 3 hFErMB 6 Tranu's lik r . lAll Bkr. 1 A13 TIA-1 & lockout lockout TlA-2 Itelay flelay ,
We ul,e 'J 't v ope rute:d Oierated 0, -o ru i.. :.1 86/lAlI 8Is/l Al'i
- n. D >
D-3 Dh D4 D -6 m
1%rl Calhoun .s,at ion Unit flo.1 OP 10 ...o-2 Operatind l*rocedure flo.
Annuncialor A-16 10._ 30 Y, Panel Cli-po O , .
Tely Get Point JAN 1 a 1979 Tecu.sp$c.
Ui nilr.u Alarm Device (lleset) Corrective Action tiercrence A-1 Trans former TI Al Contact opera- Level low Mark Auto: Alarm 27 of1 Level 1.ow tion of gauge on gauge Follow-up-Check for oil con t, acts Temp. 90 C. leak and excessive Oil leak or cooler / fun R-2 Trnauformer T1 A-1 Secondary 27-lX 3115 volts Auto: Alarm 27 Low VolLuge 1Al-13 Follow-up-Check generator and or 3h5 KV voltage for 27-2x 3115 volts malfunction. 1r unable 1Al-13 to clear alarm, transrer or bus power to 161 KV rysten 2'(-Th h003 volts ir voltage below 3115V.
TIA1 A- 1 Tranurormer TlA-l Contact opera- Trans former Auto: Alarm 141f.oV Duu Grountleil Lion on ground faul t, or 41160V Follow-up-Locate grounded 2*7 rault, relay equipment component wit,h rault 6hX/1Al-D ruulL. locator and de -enet gize ir plant conditions allow Cont,act electrical mai nt.cnance .
A. I. 16h,o VolL hua Trans '
Cont. net from 22KV uyatem flotify: 906 2.7 To . ;'t;V lilocheil cynch-check Electrical Maint,.
out or synch relay 25-1/G1 wiLh IblKV or Check: Relays /Plud3 or umler-frey . gen. Treal . flot i ry: Sys t.cm pro t.ec t.J on relay 81/G1 ';911z. for check prior t.o resetti Ig any flugs/reluys. Do not.
v . . . . . . . . . . . . . . _ _ g .. .-
J_!crformJia_y_ hut. bun _tra nu_l _ _ _ _ _ _ - -
( O OP-10-A 1 Fort Calhoun Station Unit flo 1 Operating Procedure No. 10 g {p .
[
Annunciator A-17 -
l Punel CB-20 l
(( ,5
..g,y.
Trans TIA-3 f!'rans T1 A-3 rans TlA-3 4160 Volt 1160V Bus 4 Fire Sprink- Aux. Bldg. h80V Bus h80V Trans Oil level Secondary ,
)}a 0 V Bus Bus Trans 1Al-1A3 ler Diesel Deluge Ib3A, IB3B Secondary lu 011 Terni Iow Voltage ' 1round to 161KV Trans fer RM-1 Valve open & IB3C Ekrs. Trip /
lli .
Blocked Off Auto Actuated Ground Off Ilorng41
,,,_ ,, A-1 x _ x A-2, ' M-3 A Is . A-S A-6 A-7 A-9 Trans TIA-3 4160 Bus lA (h160VBusL Diesel Bkr. h80V Bus 480V bus lADI 183A, IB3B( Tie lira.
Win.fing Te n.p . Ili Trans 1A3 FeedersEkr[.Iow Voltagt ) Trip & IB3C Iow Trip /Orr Auto Trip Voltage ' ilornal f
B-1 B-2 y B-3 ) Bli B-S B-6 B- . .. B-8 ) Ib9
~ I; 7; --
l Trans Tl A .3 Trans TI A-3 Bkr. Y Ekr.1A33 OPLS Jock - Diesel B- I /1U30-l'rcuu u re das Auto Trip Auto Trip out helay D1 Over- fi fi lab II11 B Hulay Oper l'ress Relle Test Switch load lli C 12 V I B C 12 V Open Ch. A DC Transfer DC Transfer Sw. Off Sw. Duerd.
flormal Supply Off C-1 C-2 C-3 C-4 C-S C-6 C-7 C-8 g., rn,:.1 C-9.
Tra nu 's Trans TI A-3 bkr. JA31 Ekr. 1A33 Bus JA3 Diesel Di is80V Bus Trans.
T1.4- 3 & I.oekout Inckout lockout Inckout Lockout IB3A-hA TIB-3A/3B/
TIA-h lielay Oper Helay Oper Relay Oper 8telay Oper Relay Oper IB3B-hD 3C Winiting sie l uce vi v. 36/TIA3 86/1A31 86/lA33 86/lA3-TPB 86/D1 1D3C-h C Tennp ll1 Ope raL ed Iow Volta e D-l D-2 D-1 D-h D-Sl D-6 D-7 D- D-9__
s 1.'( 1- 2 ' 1.
. . . . . . ... .... . - .,,, .....s Operating Procedure 110. 10 -
, g , ,' ; i t.- . . op_ g o_g1 f_3 Annuneintor A-l 'f_ ; ,8 [ ,* P .
Panel - - Cil-20 e4 3 . . !
Trip det Point Tei*h . : !'re .
'f t odou
. AIntm- Device fHeaeL) Co rrec t. i vit Action He fgi_ nce A-1 Transformer TI A-3 Cont.act opera- Ievel - low Auto: Alarm 2.7 011 I,evel inw t. ion or gauge mark on gauge Follow-up-Check for oilleals Oil I.evel 111 contact.s Temp - 90 C and excessive current.
C l A-2 Transformer Tl A-3 Secondary low 27-1X 3115y Aut.o : Alarm . 2.7 Voltage 1A3-13 Follow-up-Check that alarm and is valid. Transfer power j
~
27-2X 311Sy supply from TI A3 If cause l
1A3-13 is due to low voltage.
or Cont.uct Elect.. Maint.. .
27-73 Is003V l
; TlA3 '
l JW - ,
1 I
A- 3 'frunuformer TIA-3 Contact opera- Trans former into- Alarm hidOV llos Cround tion on ground faul t o r 1160 6 Follow-up-Incate grounded 27 fault relay equipment, component with faul t lo-61s X/l A3-13 ra ul t. . cator and de-energize ir plant conditions allow.
Contact electrical main-tenance.
i j
A-h h160 Voit lius Trans Contact from 161KV out of Hotify: 906
- To 16thV filocked synch-check synch with Electrical Maint.
! relay 25-2/G1 02 22KV or gen. Check; Helays/FJugs under-freq. fregg459 liz. Ilot,i fy Sys tem l'ro tec t. ion l
relay 81/G1 6 for check prior to reset.Liig l nny flags /reluyu. Ib not. ,
8
_ . .._... _..._ __..- - perfvrm_any.ltot laus . transfers ... - . _ . . . .
when this alarm la in.
R( 3a i V w/ m.
^
f Fcrt Calhoun St Oon Unit No. 1
- Operating Proce' dure flo. 10 i op-lo-Alt-S -
Annunciator A-17 -
Panel CH-20 L uJ .
o .ro~. i
, l' li Trip Set Point Tech. Spec.
Utndow Alarm Device (Heset) Corrective Action Reference l p a
1 u-1 Transforner TIA-3 Contact opera- 120 C Auto: Alarm Winding Temp 111 tion on winding Follow-up-Heduce load on temp. gauge transformer by transferrirq auxiliaries. Determine cause of hi temp.
B-2 1:160 bus IA3 contact opera- CB-20 control Auto: Alarm 2.7 Transformer Feeder breakers tion of CB-20 switch in'the : Trips 180V 4 Auto Tri.l ped control switch after close- transformer second-and breaker position and ary breaker and associatet position. the breaker island bus tie.
open for the Follow-up-Close bus tie following breakers to feed the breakers: island and 180V bus from 4
TIB-3A, T1B-3B, Bus IAl4 after insuring TIB-30, or the trip was not a fault TIB-3D. on the bus.
Cai ty out follow-up of D f "
f le160V Bus IA3 low Voltage 27-1X Auto: Alarm 2.7 f H-3 90%
Follow-up-Verify if alarm
\ 1A3 if valid. Transfer power 27-2X supply if power supply 1Ali has malfunctioned. Conta-t
'Q ~ Elect. Maint.
' ~
, x l
# \ f M t-12-fl1
Port Calh(nin Station linit. I!o. 3 10 OperaL.ing Proccabare flo.
]..g;,( g',. j ., ; i ' * - ,'
Annnuelutor A-17
Pane 1 C8-20 '**
k ' . '. i Trip Set. Point I-,'
' Tech. Spac.
tlinden A1:trm Device (Peset) t;orrective Act.lon lie ference l
l 15-6 Diesel lireaker Contact opera- Breaker Buer- Aitto : Alarm 27 1ADI Tripped l tion in breaker gency Cont.rol : If lockout relay
; 1AD1 Switch in the 86/D1 operat.es, D2 ,
i " Trip" posi- will start.. ' Ioad I tion, control shed of Bus lA3 If I switch on no other power
' CB-20 in the supply on bus.
" Trip" posi- Follow-up-Invest.igate tion, lock- reason for trip and trans-relay 86/D1 rer emergency loads to
! provided Bus 1Als insuring D-2 ir breaker pro- operating does not exceed 4
tection over- overload rating.
I ride is not i:
e rrect. , or l! ir diesel D1 -
l, V shutdown.
it-H h80V Bus Ill3A,11338 and Ill3C 27-lX A' 90% Auto: Alarm
!aw VolLage 1B3A Verify ir valid alarm; if
\l and so, check for t.ransformer i
27-2X malfunct. ion and inform i i El" L#I "I M"I"'*"""'"'
IB3A 3 or 27-1X /
IB3B
% alld I
27-2X i 1B3B or
, 27-lX 1B3C littd i
27-2X ,
1li3C l . - . . . .. ..o._. . _
P Q _
Ir/ ,3 - 1 9 1
(~ D D OP-10-A18-1 Fort Calhoun Station Unit No. 1 Operating Procedure Ilo. 10 O {a ,
Annunciator A-18 4 -
, Panel CB-20 hO b APR 2 1983 StlGR Roorn l'80V Bus Fire Sprink31160V 4 Trans TlA 14 Trans T1A-b hfransTIA!:
ilVAC Al-187 1BsA, I 1B!B4 ler Diesel Bus lA2-1Al. 1160V Bus 4 Secondary 11 Level Irouble and.lB1C4 Hm-2 Actuat Transfer Ground Low Voltage Io 011 Temp
, Ground ed Off Auto 11 i
A-1 _ e x A-2 A-3 A le A-5 A-6 n _A-7 A-{ A,,9 480V Bus 'Is80VBub OV Bus Diesel Ekr. 1160V Bus 4
^ (1160VBus 4 h160V Trans TIA-h IB3A-hA Bus- '1 bha, IBhB 1AD2 1 A2-1 AI. V a Bus 1Ali I A!6 Trans Winding Tie Bkr. & 1BlC Iov 4 Trip 125V DC rep su ane Iow Voltage Feeder Bkrt Temp lli Off Normal , Voltage Transfer St Suppl Off' g Auto Trip B-1I B-2 Off Normal Norma B-3 B-b B-5 B-6 B _7 )
B-8 B-9 480V Bus Diesel D2 OPLS Lock Bk r. 1 Ahh BkDAD Trans T1 A l TransTik-h i
I B3B-hb Bus Overload out Relay Auto Trip Auto Trip Gas Press. Pres s ur'e Tie Breaker Test Switel Relier Relay Oper Off flormal Open Chan-4 C-1 C-2 C-3 C-h C-5 C-6 C-7 C-8 C-9 180V Bus 6 Trans. Diesel D2 Bus 1Ah Bkr. 1Ahh Ekr. 1Als2 Trans TIA l.
lb3C 1.C TIB-hA/hB/ Lockout re- Lockout re- Lockout re- Lockout re- Lockout re-Bus Tie he Winding lay Oper lay Oper lay Oper lay Oper lay Oper breaker Off Temp 111 86/D2 86/lA!-TFB 4
86/1Ah!4 86/1 Ale 2 86/TIAh flarmal p_) D-2 D-3 D la D-5 D-f, D-7 D-8 I}-S_.
R4 4-2-83
Fort (':tJ lsous I. ions lini t N.). L .
Oper:st i ng, Pr.sceilisre llo. -
Annnut Intor A-18 R * .
OP-10-A18-3 P:un!! _._C B-20 ;l ( ,
Trip Set PoJnt . Teels. Spee.
Wi nslow Alarm Device (iter:et ) Cottective Action lie ference A-7 Trans former Tl A-h Contact opera- Transformer Auto: Alarm kl60V Bus Ground tion on ground fault or 1160V Follow-up-Locate grounded 4
, fault relay equipment component with' fault lo-61sX/lAls-24 fault . cator and de-energized if plant conditions allow.
Contact electrical main-A-8 Transformer T1A-b Secondary Low 27-1X 3115V Auto: Alarm 27 i Voltage 1A1-24 4 Follow-up: Check that '
l and alarm is valid. Transfer 27-2X 3115V power supply if cause is i)-
1Als-24 due to low voltage from q or the power supply.
27-74 3980V TlAh A-9 Trans fo rmer Tl A 14 Contact opera- Level - Low Auto: Alarm Oil Level Lo tion of gauge mark on gauge Follow-up-Check for oil Oil Temp. !!i contacts. Temp - 90 C. leak and excessive Cause - oil current leaks.
T .
ForL Cullusun 1.i.alion IJni L flo. 1 ..
Operating Procedure IJo. In Annunciator A-18 OP-10-A18 le Punel ~
CB-20 I *'t 3g yx s[j, 3 , .I @
Trip Uet, Point Tee ls . : l *ee .
Wi enlow Alarm Device (it er,et ) Correct!ce i.etion lie ference B-1 180V Bus 1B3A IsA 4
Contact opera- Bus tie Auto: Alarm 27 Bus Tie Breaker tion of breaker breaker Follow-up-Return bus Off Normal BT-1 bha BT-lbl A 4 1B3A 1A to normal line 4
closed, up as soon as possible to insure a separation e [ ~
of safeguard loads.
B-2 180V B.is 1B4 4 l A,1Bl B, & IBl:C 4 27-1X 90 2.7 Low Voltage 1 bha Follow-up: Verify if a and valid alarm. If so, 27-2X check transformers for (
1Bl A 4
""I'""U " "" # "
,'w- Electrical Maintenance.
or 27-1X 1Bhb l \\
and 27-2X 1BhB or 27-lX IBl C 4
/
and 27-2X 13hC
.---_./ - . . - - . - - - -
p -
--R--------
I
] .
*orL C: !hean Si/it. ion linil :10 .1 OP-10-A18-6 .,
Opern Li rad i't occuner 11 . J 0.
- Annunelater A-18 l' ui.r l. CB-20 . t .
Trip liet Point Tech. U'ee.
l 1/i ndc's Alarm ._ _. Devire ._ (Re M k D r'ecijve Action _ Heference N" Mr N V N N
~
V '
j
( B-7 4160 V Bus IAl4 Low Voltage 27-1X 90% Auto: Alarm 27 l 1A14 Follow-up: Verify if alarm valid. Transfer 27-2X power supply if power IAh supply has malfunctioned.
/
I l l l
l e
B-8 h]60V Bus lAh Contact opera- CB-20 Control Auto: Alarm 2. ~l l Trans former Feeder Breakers tion of CB-20 switch in the : Trips h80V trans-Aut > Trip control switch after close former secondary ,
and breaker position and breaker and assoc-position. l
. the breaker lated island bus j open for the tie. !
l following Follow-up-Close bus tie i breakers: breakers to feed the 5 i TlB-hA, island and 480V bus from l TIB-hB, Bus lA3, after insuring i j TIB-hC, and the trip was not a fault i I tlc-hA. on the bus.
I l 1'
i i ,
i I l i i I
i i l
.e h .
i
.--p--.-.-....----...----..---.--....-...-... .
.m . -
V ) '
OP-10-Ai9-1 ,',
Fort Calhoun Station Unit lio. 1 Operating Procedure lio. 10 Annunciator A-19 3 gg{
Panel CB-20 s . . .
8 8 I
I 3 '
j s A-
. A
; i Trans T1A-2 Trans TIA-2) Trans 'I'1 A-2
. 1:160V Bus 5 Secondary '011 Level Ground / LowVoltagI Lo 011 Temp -
( 111 A-3 A-b ( A A A-1 A-2 hl60V Bus
_ -5 Trans T1A-2 DC llus #2 ,
1A2 Iow Winding I Gropnd Voltage Temp 111 I
. B-1 B-2 R-3 B 14 B-5 B-6 ,
i Bkr. 1A24 Ekr. lA22 Trans T1A-2 Trans TIA-2 Auto Trip Auto Trip Gas Presa. Pressure l flelier Relay Oper C-1 C-2 C-3 c-4 C-s C-6 i Panel Bkr. lA24 Bkr. lA22 Low Voltagt Weattwr'
, AI-blB Lockout Iockout AC Iluses Tower i
Transfer Relay Oper relay oper IA and 2A Trouble 8 Sv. E=ai g 86/1A214 86/1A22 UC UI8t* #
l ~
Supply Ort g Pnlo.1 G ,'h6
. D-1 Normal D-2 D-3 .
116 12-3-81
() O Fort Calhoun St.ation IJnit 11o.1 OP-10-A19-2 O ,
OpernLing l'roccature llo. 10-Annuneintor A-19 -
j Panel en_9n DEC 3 1981 -
Trip Set: Point Tech. C.ec. l I Ui nelow Alarm Device (Reset) Corrective Action Re fere:nce l A14 Transformer TI A-21160V Bus 4 Contact opera- Transformer Auto: Al' arm Cruund tion on ground fault or Follow-up-Locate grounded ,
j fault relay 14160V equip- component with fault lo- '
l 61X/lA2-214 4 ment fault. cator and de-energize if l plant cotiditions allow.
Contact electrical O y maintenatice. q LA-5 Transformer TlA-2. Secondary 27-lX 311SV Auto: Alam 27 i [\ Iow Voltage 1A 2-214 and Follow-up-Verify alarm.
Check gen. and 315 KV volt-4 l
s 27-2X 3115V age. Transfer bus power 1A2-214 supply if bus is being fed or frcm affected power supply i
27-71:
TIA2 3980V j l
^
1
, t A-6 .
Transformer TlA-2 Contact opera- Level - Iov Auto: Alarm 011 Level In t. ion of gauge mark on gauge Follow-up-Check for oil 011 Ten.p 111 contacts Temp - 90 C. leak and exceanive current Ensure cooling fans are in operation.
g 6-~1F'F s~l~ ~f ' -' ~ ~ ~ ~ ~ ~ '
h}}