|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999
Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached
ML20217G9261999-10-15015 October 1999
Forwards Insp Rept 50-285/99-10 on 990913-17.One NCV Noted
ML20217G2331999-10-14014 October 1999
Forwards Insp Rept 50-285/99-09 on 990913-17.No Violations Noted
LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999
Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util
LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999
Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls
ML20217B5111999-10-0606 October 1999
Forwards Amend 193 to License DPR-40 & Safety Evaluation. Amend Revises TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance require- Ments for RCS Flow Rate
ML20216H7231999-09-29029 September 1999
Informs That Util 980325 Response to GL 97-06, Degradation of SG Internals, Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Fort Calhoun Station,Unit 1
ML20212L9571999-09-27027 September 1999
Informs That Follow Up Insp for Drill/Exercise Performance Indicator Will Be Conducted During Wk of 991001
LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999
Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl
LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999
Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl
LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999
Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams
LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999
Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls
LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999
Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection
LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999
Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters
IR 05000285/19990081999-09-0707 September 1999
Forwards Insp Rept 50-285/99-08 on 990907-0811.No Violations Noted.Insp Consisted of Exam of Activities Conducted Under License as Relate to Safety & to Compliance with Commission Rules & Regulations & with Conditions of License
ML20211P2581999-09-0303 September 1999
Forwards Insp Rept 50-285/99-06 on 990809-12.No Violations Noted.Insp Consisted of Exam of Activities Under License as Related to EP & to Compliance with Commission Rules & Regulations & with Conditions of License
LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999
Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase
ML20211J9231999-09-0202 September 1999
Forwards SE Accepting Licensee 990301 Requests for Relief Re Third 10-year ISI Interval for Plant,Unit 1.Relief Proposed Alternatives to Requirements in ASME B&PV Section XI,1989 Edition,Paragraphs IWA-5242(a) & IWA-5250(a)(2)
ML20211L3241999-09-0202 September 1999
Informs That Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) of Amend 192 to License DPR-40 Issued on 990727.Corrected Page Encl
LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999
Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld
ML20211F4491999-08-25025 August 1999
Forwards Ltr from Ja Miller,Dtd 990819,which Notified State of Iowa of Deficiency Identified During 990810,Fort Calhoun Station Biennial Exercise.One Deficiency Identified for Not Adequately Demonstrating Organizational Capability
LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999
Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)
LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999
Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld
ML20210R1491999-08-13013 August 1999
Forwards Insp Rept 50-285/99-07 on 990719-23.No Violations Noted.Nrc Identified One Issue Which Was Evaluated Under Risk Significance Determination Process & Was Determined to Be of Low Risk Significance
LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20211B7881999-08-10010 August 1999
Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714
ML20210N1991999-08-0909 August 1999
Informs That as Result of NRC Review of Licensee Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2
ML20210P8991999-08-0909 August 1999
Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill
LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999
Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999
Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999
Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331
LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999
Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program
ML20210G1851999-07-27027 July 1999
Forwards Amend 192 to License DPR-40 & Safety Evaluation. Amend Consists of Changes to TS in Response to 990129 Application
LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999
Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630
ML20216D6951999-07-26026 July 1999
Informs That During 990614 Review of Fort Calhoun,Nrc Noted That Drill/Exercise Performance Indicator Has Entered White Band,Which Indicated Level of Licensee Performance That Warranted Increased Regulatory Response
LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999
Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates
LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999
Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld
ML20210D9471999-07-22022 July 1999
Forwards Amend 191 to DPR-40 & Safety Evaluation.Amend Authorizes Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation
ML20210C2041999-07-20020 July 1999
Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations
ML20210C0201999-07-20020 July 1999
Informs That Due to Administrative Oversight,Revised TS Bases Provided in to Fort Calhoun Station Were Not Dated.Dated Pages to TS Encl
ML20210B0761999-07-19019 July 1999
Forwards Insp Rept 50-285/99-05 on 990601-0710.No Violations Noted
ML20209G5351999-07-15015 July 1999
Informs That Staff Incorporated Rev of TS Bases Provided by Licensee Ltr Dtd 980904,into Fort Calhoun Station Tss. Staff Finds Revs to Associated TS Bases to Be Acceptable. Revised Bases Pages Encl
ML20209F5741999-07-12012 July 1999
Ack Receipt of Transmitting Exercise Scenario for Upcoming Biennial Offsite Exercise Scheduled 990810.Scenario Reviewed & Acceptable
ML20209G5591999-07-0808 July 1999
Forwards Detailed Listing of Staff Concerns with C-E TR NPSD-683,rev 3 & RCS pressure-temperature Limits Rept
LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999
Forwards Fort Calhoun Performance Indicators Rept for May 1999
LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999
Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld
ML20209D8771999-07-0101 July 1999
Summarizes 990630 Public Meeting Conducted in Fort Calhoun, Ne Re Results of Completed Culture Survey,Plant Status, Facility Activities Re New NRC Oversight Process & License Renewal.Licensee Handout & Attendance List Encl
LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999
Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999
Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached
LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999
Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util
LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999
Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls
LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999
Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl
LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999
Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl
LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999
Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams
LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999
Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls
LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999
Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection
LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999
Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters
LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999
Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase
LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999
Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld
LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999
Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld
LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999
Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)
LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required
LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999
Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable
LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999
Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999
Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331
LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999
Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program
LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999
Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates
LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999
Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630
LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999
Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld
LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999
Forwards Fort Calhoun Performance Indicators Rept for May 1999
LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999
Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld
LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999
Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624
LIC-99-0061, Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl1999-06-30030 June 1999
Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl
LIC-99-0056, Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-061999-06-22022 June 1999
Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-06
LIC-99-0059, Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning1999-06-22022 June 1999
Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning
LIC-99-0054, Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 9908101999-06-0808 June 1999
Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 990810
LIC-99-0052, Forwards Fort Calhoun Station Performance Indicators, for Apr 19991999-06-0202 June 1999
Forwards Fort Calhoun Station Performance Indicators, for Apr 1999
LIC-99-0045, Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl1999-05-26026 May 1999
Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl
LIC-99-0046, Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise1999-05-12012 May 1999
Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise
LIC-99-0028, Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage1999-04-30030 April 1999
Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage
LIC-99-0036, Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F1999-04-28028 April 1999
Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F
LIC-99-0043, Forwards Fort Calhoun Performance Indicators Rept for Mar 19991999-04-28028 April 1999
Forwards Fort Calhoun Performance Indicators Rept for Mar 1999
LIC-99-0041, Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager1999-04-27027 April 1999
Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager
LIC-99-0037, Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue1999-04-26026 April 1999
Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue
LIC-99-0039, Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a1999-04-20020 April 1999
Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a
LIC-99-0038, Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl1999-04-20020 April 1999
Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl
LIC-99-0033, Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps1999-04-15015 April 1999
Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps
LIC-99-0035, Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure1999-04-0808 April 1999
Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure
LIC-99-0031, Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate1999-03-31031 March 1999
Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate
LIC-99-0032, Forwards Fort Calhoun Station Performance Indicators, for Feb 19991999-03-31031 March 1999
Forwards Fort Calhoun Station Performance Indicators, for Feb 1999
LIC-99-0029, Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques1999-03-30030 March 1999
Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques
LIC-99-0027, Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld1999-03-16016 March 1999
Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld
LIC-99-0022, Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl1999-03-12012 March 1999
Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl
LIC-99-0024, Informs That OPPD Withdraws Applications Submitted by 950626 &1999-03-12012 March 1999
Informs That OPPD Withdraws Applications Submitted by 950626 &
LIC-99-0016, Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives1999-03-0101 March 1999
Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives
LIC-99-0023, Forwards FCS Performance Indicators for Jan 19991999-03-0101 March 1999
Forwards FCS Performance Indicators for Jan 1999
LIC-99-0020, Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included1999-02-24024 February 1999
Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included
LIC-99-0011, Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 11999-02-0505 February 1999
Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 1
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARLIC-90-0705, Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl1990-09-17017 September 1990
Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl
LIC-90-0745, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions1990-09-17017 September 1990
Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions
LIC-90-0717, Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-071990-09-13013 September 1990
Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07
LIC-90-0716, Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls1990-09-13013 September 1990
Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls
LIC-90-0740, Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits1990-09-12012 September 1990
Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits
LIC-90-0741, Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets1990-09-0707 September 1990
Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets
LIC-90-0440, Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes1990-09-0606 September 1990
Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes
LIC-90-0667, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 9005291990-09-0404 September 1990
Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 900529
LIC-90-0712, Forwards fitness-for-duty Program Performance Data for Period of Jan-June 19901990-08-31031 August 1990
Forwards fitness-for-duty Program Performance Data for Period of Jan-June 1990
LIC-90-0683, Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations1990-08-27027 August 1990
Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations
LIC-90-0627, Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection1990-08-22022 August 1990
Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection
LIC-90-0670, Forwards Fort Calhoun Station Performance Indicators for Jul 19901990-08-22022 August 1990
Forwards Fort Calhoun Station Performance Indicators for Jul 1990
LIC-90-0662, Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution1990-08-22022 August 1990
Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution
LIC-90-0673, Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl1990-08-22022 August 1990
Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl
LIC-90-0636, Forwards Results of 1990 Refueling Outage Inservice Insp & Rept for Repairs or Replacement1990-08-13013 August 1990
Forwards Results of 1990 Refueling Outage Inservice Insp & Rept for Repairs or Replacement
LIC-90-0591, Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-21990-08-13013 August 1990
Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-2
LIC-90-0631, Responds to Generic Ltr 89-15 Re NRC Solicitation of Utils to Voluntarily Participate Emergency Response Data Sys Program.Util Prepared to Work W/Nrc to Investigate Actions Necessary to Implement Program at Plant1990-08-0808 August 1990
Responds to Generic Ltr 89-15 Re NRC Solicitation of Utils to Voluntarily Participate Emergency Response Data Sys Program.Util Prepared to Work W/Nrc to Investigate Actions Necessary to Implement Program at Plant
LIC-90-0485, Confirms Interim Resolution of Identified Problem Associated W/Use of Input Variable for PORV Opening Time in Calculation of Low Temp Overpressure Protection Sys Setpoints1990-08-0707 August 1990
Confirms Interim Resolution of Identified Problem Associated W/Use of Input Variable for PORV Opening Time in Calculation of Low Temp Overpressure Protection Sys Setpoints
LIC-90-0645, Forwards Application for Amend to License DPR-40,making Typo & Administrative Corrections to Tech Specs1990-08-0202 August 1990
Forwards Application for Amend to License DPR-40,making Typo & Administrative Corrections to Tech Specs
LIC-90-0647, Informs That Tl Patterson Assumed Position of Plant Manager, Effective 9008011990-08-0101 August 1990
Informs That Tl Patterson Assumed Position of Plant Manager, Effective 900801
LIC-90-0659, Advises of Plans to Achieve Operability of Third Auxiliary Feedwater Pump by 9008101990-07-31031 July 1990
Advises of Plans to Achieve Operability of Third Auxiliary Feedwater Pump by 900810
LIC-90-0449, Forwards Rev 1 to EA-FC-90-037, Control Room Habitability Evaluation for NUREG-0737,Item III.D.3.41990-07-20020 July 1990
Forwards Rev 1 to EA-FC-90-037, Control Room Habitability Evaluation for NUREG-0737,Item III.D.3.4
LIC-90-0588, Provides Notification of SPDS Implementation at Plant,Per1990-07-19019 July 1990
Provides Notification of SPDS Implementation at Plant,Per
LIC-90-0585, Forwards Simulator Malfunction Cause & Effects1990-07-18018 July 1990
Forwards Simulator Malfunction Cause & Effects
LIC-90-0581, Informs That Requirements of NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount Satisfied.None of 48 Transmitters in Use at Plant Exhibited Symptoms Indicative of Fill Oil Problems Since Installation in 19871990-07-18018 July 1990
Informs That Requirements of NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount Satisfied.None of 48 Transmitters in Use at Plant Exhibited Symptoms Indicative of Fill Oil Problems Since Installation in 1987
ML20055D9351990-07-0202 July 1990
Forwards Fort Calhoun Station Performance Indicators,May 1990
LIC-90-0564, Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility1990-06-29029 June 1990
Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility
LIC-90-0522, Forwards Revised Response to Notice of Deviation from Insp Rept 50-285/90-02.Corrective Actions:Cable Trays 5-4A & 5-4B Reworked to Neatly Tie Down Cables & Remove Crossovers & Engineering Instruction GEI-9 on Electrical Sys Updated1990-06-29029 June 1990
Forwards Revised Response to Notice of Deviation from Insp Rept 50-285/90-02.Corrective Actions:Cable Trays 5-4A & 5-4B Reworked to Neatly Tie Down Cables & Remove Crossovers & Engineering Instruction GEI-9 on Electrical Sys Updated
LIC-90-0566, Forwards 1990/1991 Statement of Cash Flow from Operations. Cash Flow Statement Deviates from Reg Guide 9.4 Due to Util Being Political Subdivision of State of Ne1990-06-29029 June 1990
Forwards 1990/1991 Statement of Cash Flow from Operations. Cash Flow Statement Deviates from Reg Guide 9.4 Due to Util Being Political Subdivision of State of Ne
LIC-90-0488, Responds to Request for Info Re Status of Implementation of Generic Safety Issue Requirements1990-06-29029 June 1990
Responds to Request for Info Re Status of Implementation of Generic Safety Issue Requirements
LIC-90-0446, Forwards Application for Amend to License DPR-40,to Restrict Containment Spray Use as Backup for Shutdown Cooling in Tech Specs1990-06-28028 June 1990
Forwards Application for Amend to License DPR-40,to Restrict Containment Spray Use as Backup for Shutdown Cooling in Tech Specs
LIC-90-0429, Forwards Application to Amend License DPR-40,adding Hydrogen Purge Sys to Tech Spec.Discussion,Justification & NSHC Analysis for Amend,Provided1990-06-28028 June 1990
Forwards Application to Amend License DPR-40,adding Hydrogen Purge Sys to Tech Spec.Discussion,Justification & NSHC Analysis for Amend,Provided
ML20044A1631990-06-22022 June 1990
Requests That NRC Continue Processing Exemption Request for Configuration of wide-range Nuclear Instrumentation Cables in Fire Area 34B (Upper Electrical Penetration Room). Emergency Boration Added to Achieve Safe Shutdown
ML20043J0611990-06-22022 June 1990
Responds to NRC 900523 Ltr Re Violations Noted in Insp Rept 50-285/90-29.Corrective Actions:Five Chemistry Technicians Provided Refresher Training on 900427 on Existing EPIP-EOF-6
ML20044A4961990-06-18018 June 1990
Forwards Supplemental Application for Amend to License DPR-40,making Administrative Corrections to Tech Specs. Procedure SO-G-70, Chemical Control Also Encl
ML20043G2981990-06-14014 June 1990
Provides Followup to Special Rept on Inoperable Fire Barriers.Eight Inoperable Dampers Replaced Under Mod MR-FC-87-036, Fire Damper Replacement. Remaining 38 Dampers Found to Be Acceptable After Damper Design Review
ML20043E6451990-06-0808 June 1990
Provides Supplemental Response to Generic Ltr 88-17 & NRC Bulletin 80-12.Plant Pumps & Suction Header Piping Not Originally Constructed for Use as Backup to LPSI Sys for Shutdown Cooling
ML20043G3281990-06-0101 June 1990
Advises That Personnel at Util Reviewed Reactor Operator Licensing Exam Administered on 900529.Comments on Exam Encl
ML20043E0071990-06-0101 June 1990
Discusses Rev to Previous Commitments Made in Response to Requirements of 10CFR50,App R,Section Iii.G Re post-fire Repairs to Equipment Required for Cold Shutdown Following Fire in Fire Area 6
ML20043C1811990-05-29029 May 1990
Advises That Util Has Cleaned RW HXs AC-1A & AC-1D & Will Clean AC-1C by 900615
ML20043B4981990-05-24024 May 1990
Updates Schedule for Submitting Results of PORV Block Valve Prototype Testing.Establishment of Test Parameters & Development of Test Procedures Tentatively Scheduled for Submittal in Nov 1990.Final Rept Expected by 910630
ML20043B5061990-05-23023 May 1990
Advises That Testing to Verify Operability of Hydrogen Purge Sys Successfully Completed During 1990 Refueling Outage.Proposed Tech Spec Rev Will Be Submitted by 900701
ML20043B4731990-05-23023 May 1990
Forwards Fort Calhoun Station Performance Indicators, Monthly Rept for Apr 1990
ML20043A8021990-05-18018 May 1990
Advises That Walkdown of safety-related Portions of Plant to Verify Accuracy of Fire Barrier Penetration Drawings & Surveillance Tests Will Be Completed by 900831
ML20043A7821990-05-18018 May 1990
Advises That Licensee Plans to Replace Valves HCV-247 & HCV-2988 During 1991 Refueling Outage Pending Successful Redesign & Retesting of New Valves by Valcor
ML20043B0391990-05-16016 May 1990
Informs of Current Status of Post Accident Sampling Sys. Program Meets Min Requirements & Fulfills Conditions of Tech Spec 5.15
ML20042G9861990-05-11011 May 1990
Forwards Rev 0 to Interim Operability Criteria (Ioc) Criteria for Performing Safety Analysis for Interim Operability of Piping, Resulting from Discussion at 900306 & 0418 Meetings
ML20042G9571990-05-10010 May 1990
Forwards Suppl to Application for Amend to License DPR-40, Making Administrative Clarification to Chloride Sampling Requirements.Standing Order Procedure S.O.-M-10, Tool Accountability Also Encl
ML20042H0021990-05-10010 May 1990
Fowards Fort Calhoun Station Performance Indicators,Mar 1990, Monthly Rept
ML20042G9981990-05-10010 May 1990
Forwards Proprietary & Nonproprietary Rev 13 to EPIP-EOF-18, Offsite Radiological Surveys.
1990-09-07
[Table view] |
Text
'
Omaha Public Power District 1623 Harney Omaha, Nebraska 68102-2247 402/536-4000 March 13, 1987 LIC-87-126 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Reference:
- 1. Docket No. 50-285
- 2. OPPD Application for Amendment of Operating License dated March 21, 1986 Gentlemen:
SUBJECT:
Diesel Generator Technical Specifications The Omaha Public Power District submitted, via Reference 2, an application to amend the Fort Calhoun Station Technical Specifications relative to testing of the emergency diesel generators. This application was intended to complete OPPD actions relative to Generic Letter 84-15. Several conference calls were held with the staff's reviewer to discuss questions. The reviewer's questions have been answered in the attached pages.
The changes have been reviewed by OPPD's Plant Review Committee and the offsite Safety Audit and Review Committee. The revised discussion elaborates on the changes made, and should facilitate your review. As OPPD understands it, this l
submittal is the final step in the review process, so amendment issuance can be made. OPPD respectfully requests 60 days from the date of amendment letter to allow for implementation.
Sincerely, R. L. Andrews Division Manager Nuclear Production RLA:rge 8703190001 870313 5 Attachment ADOCK 0500
%DR c: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Ave., N.W.
Washington, DC 20036 Mr. A. C. Thadani, NRC Project Director
)') -'s de
't y(
Mr. W. A. Paulson, NRC Project Manager (original attachment) 1 Mr. P. H. Harrell, NRC Senior Resident Inspector I n w., i mewn..ms an r com oppmun,m M.lle I t*mMP
2.0 LIMITING CONDITIONS FOR OPERATION .
2.4 containment Cooling (Continued) component cooling heat exchangers and shutdown heat exchangers. A full-capacity diesel-generator is connected to each of the two engineered
, safeguards 4.16-kV buses. Three engineered safeguards 480-Volt double-ended load centers are provided; of the six transformers, three are connected to each of the two 4.16-kV buses. Two load centers are operated as two-bus-section units; the third is provided with a center bus manually transferable to either associated end section. The center bus section supplies HPSI Pump SI-20, CS Pump SI-3C and Charging Pump CH-lc any of which can thus be supplied from either k.16-kV bus if required.(with capacity Threecaponentcoolingheatexchangegshavesufficient ample rese ) to remove 420 x 10 BTU /hr following a loss-of-coolant accident. The containment spreys initially take coolant from the safety injection and refueling water (SIRW) t Before this supply of water is exhausted (at lesat 24 minutes)g.
the spray system is transferred to the recirculation mode and the pumps take suction from the containment sump. One shutdown cooling heat ex-changer is sufficient to satisfy the spr gystem requirements during the long-tem containment cooling period. 3i In addition, in the un-likely event of the component cooling water supply being lost, raw water can be utilized for dire cooling of the shutdown heat exchangers and containment cooling coils.
The containment spray system is redundant with the containment air recirculation, e ng and iodine removal system for the containment cooling function. The spray system is sized such that two of the three spray pumps would limit the containment pressure to below the j -
design value following a DBA without taking credit for $ air coolers i or the cooling capacity of the safety injection system.tp1 Similarly, i
two cooling and filtering units or one cooling and filterin6. unit and both pressure cooling underunits the have same the capability conditions of limiting as two the(e Intainment spray pumpn The redundant cooling equipment provided to limit the containment pressure following a DBA is divided between the independent power supply systems. The raw water and component cooling water pumps are similarly distributed on the 4.16-kV and 480 Volt buses to serve the above cooling groups. Each cooling group has a design capacity equal to that required to restrict the containment pressure to below the design value. In the event of a DBA, loss of normal power sources and failure of one diesel-generator to operate, better than one full group _
would be connected to the available diesel-generator, thus providing more than ample reserve. Any one unit removed from a given bus does not restrict the groups which can be connected to one diesel-generator fra fulfilling their design function. The removal of two units from buses which can be connected to one diesel-generator could limit the capability of the associated cooling groups; therefore, to ensure i availability of the power supply to the redundant equipment in the '
event of loss of normal power sources, the diesel-generator serving 1
this redundant equipment is started-to demonstrate operability. During 4
s, nn. ivt .edhrei
. - - . _ _ _ _ . _ _ - - _ _ _ . - _ - . W-_-- - _ . - _ _ _ - . - _ _ _ _ - _ _ - .
'\
3 A .. ,
3 ,-
, s s...
<~-.s ,
(
s TABLE 3-2 (continued)
MINIMUMFREhUENCIES-FORCHECKS.CALIBRATIONSANDTESTINGOF u
f ,' l ENGINEERED SAFRTY FEATURES, INSTRUMENTATION AND CONTROLS f
g
[
Channel Description
- Surveillance Function Frequency Surveillance Method z
,o 6.s(continued) b. Calibrate R b. Exposure to known ' external
's, radiation source.
c s. , s.'
_ . 1__ c. Test M c. Remote operated integral g
radiation check source used to verify instrumentation ,
one channel at a time, and isolation lockout relay functional check.
y 7 Manual Safety Injection a. Test R a. Manual initiation.
M) Initiation
- 8. Manual Containment Isol- a. Test R a. Manual initiation.
. ation Initiation
- b. Check R b. Observe isolation valves closure. ,
9 Manual Initiation Con- a. Test R a. Manual switch operation;
? tainment Spray pumps and valves tested separately.
- 10. Automatic Load Seg'oencers a. Test Q a. Proper operation vill be verified during safety -
feature actuation test of Item 3(a) above.
. 11. icac1 tar - TO $st --
.a. Manual -initiation 4ol-lowed by--synchronizing and loading.
4 L_-a &uA__. :1- ,
- . , /_ '
/ /
TABLE 3-2 (continued)
MINILfUM FREQUENCIES FOR ClfECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY PEATURES, INSTRIIMENTATION AND CONTROLS Surveillance' -
Channel Description Function Frequency Surveillance Method
- 11. (rnntinued) b,--- Te s t "
- b. Dicccic .;ill tc .; tarted duriq ccrety feature-ectuaticr. tect Of 3(a) aboec.
- c. Test B c. Diesel--steet , Icad ched , cyr
-ebroni sing--and-load ing-will-be vari tie & during -Item-3( b )-abover dr ' Pest- I' d- -Diesel-autretart--init-iating-ei r-ouits,-
w
. ,L 12. Diesel Fuel Transfer a. Test M a. Pump run to refill day tank.
Pump 13 SIRW Tank Low Level a. Check .S a. Verify level indication between Signal independent channels. .
- b. Test M b. A test pressure simulating the tank level is applied to each tank bubbler, one at a time.
- c. Caliin alo R c. Known level signal applied to sensors and STLS logic verified.
114 Safety Injection Tank a. Check S a. Verify that level and pressure Level and Pressure In- indications are between indepen-struments dent high and low alarms for level and pressure.
0 9
3.0 SURVEILLANCE REQUIREMENTS 3.7 Emergency Power System Periodic Tests Applicability Applies to periodic testing and surveillance requirements of the emergency power system.
Objective To verify that the emergency power system vill respond promptly and properly when requir-d.
+
Specifications llowing tests,and surveillance shall be perfomed as stated: /
Th (1) ' Diesel Generators Each diesel engine shall be started once a month an d ,/
- a. g\ demonstrated to be ready for loading within 10 se. ,
\e., the diesels shall be tested' alternately vo v ntervals, not both together). The sign .hitiated to the diesel shall be varied from on st to anoth o verify all manual and auto star 1r'cuits.
This tes, ' 11 cover all local and remo ' ontrols for both norma ' d emergency manual condi s.(1) .
5 minu s while s /
,A 7
/ d.
ts generator is loaded with the emergency loa control of diesel generators and breakers shall% .so be verified during refueling shutdowns, Each diesel generator shall be given a thorough inspection at least annually following the manufacturer's recommendat(ons Manual g
A- for this class of standby service. The above tests vill e
..f Amendment No. 41 3-58 ,
- 3. 0 CURVEILLANCE REQUIREMENTS
- 3. 7 Emergency Power System Periodic Tests (Continued)
[ consid ed sati actorkifalla licable equipment oper-
- es as esigned. This 9 11 inclu e calib tion of moni-to.ing in rumenta on.
---____a..
%eplac.ec.hd u ,__ _ -
m ___, _t e
, . .atw
(
C ,,::; r.. '-_ r xm.-a 7 -~ ~ v su
. r _u N ';,;_ L_ 3__
The *'uel oi trans r pumps hall b verifie to be o r-ble ch mon h.
(2) Station Batteries
- a. Every month the voltage of each cell (to the nearest 0.01 volt),
cell in the eachspecific batterygravity, shall.be and temperature measured of a pilot and recorded.t 3) (h)
- b. Every three months the specific gravity of each cell, the temperature reading of every fifth cell, and the amount of -
water added shall be measured and recorded. During the j first refueling outage and every third refueling outage l thereafter the batteries shall be subjected to a rated load -
discharge test.
- c. At monthly intervals the third battery charger, which is capable of being connected to either of the two D.C. dis-tribution buses, shall be paralleled in turn to each D.C.
bus. In each case, load shall be transferred to this re-serve battery charger by switching out the normal charger.
The reserve charger shall be run on load for 30 minutes on each bus and the system shall finally be returned to normal.
- d. During refueling shutdowns the correct function of all D.C.
emergency transfer switches shall be demonstrated by manual transfer of normal D.C. supply breakers at the 125 volt D.C.
distribution panels.
(3) Emergency Lighting The correct functioning of the emergency lighting system shall be verified at least once each year.
(4) 13.8 Kv Transmission Line The 13.8 Ky transmission line vill be energized and loaded to minimum shutdown requirements at each refueling outage following installation.
3-59 AmendmentNo.[ _
~
m fe .
3.0 -
p3 y n psaw JA 3.1 EW
{p /m I7 Jeu yhu
SPECIFICATIONS \ -
THE FOLLOWING TESTS AND SURVEILLANCE SHALL BE PERFORMED AS STATED:
i (1) DIESEL GENERATORS A. EACH DIESEL ENGINE SHALL BE STARTED AT LEAST ONCE PER
- ' 31 DAYS ON A STAGGERED BASIS. THE ENGINE SHALL BE RUN WITH ALL PROTECTIVE DEVICES OPERABLE. THE TEST SHALL VERIFY THAT:
[. THE DIESEL STARTS AND ACCELERATES TO RATED SPEED AND VOLTAGE IN LESS THAN OR EQUAL TO 10 SECONDS.
NORMALLY, FOR THE PURPOSE OF THIS SURVEILLANCE
! TESTING, THESE DIESEL GENERATOR STARTS MAY BE PRECEDED BY AN ENGINE PRELUBE PERIOD AND/OR OTHER
- WARM-UP PROCEDURES RECOMMENDED BY THE MANUFACTURER SO THAT MECHANICAL STRESS AND WEAR ON THE ENGINE IS MINIMIZED.
i
. HOWEVER, AT LEAST ONCE PER 184 DAYS IN THESE
] SURVEILLANCE TESTS, THE 10 SECOND DIESEL GENERATOR ,
START SHALL BE PERFORMED FROM AMBIENT CONDITIONS i (COLD START).
I THE SIGNAL INITIATED TO START THE DIESEL SHALL BE VARIED FROM ONE TEST TO ANOTHER TO VERIFY ALL MANUAL AND AUTO START CIRCUITS.
22 . WITH THE DIESEL RUNNING AT RATED SPEED AND VOLTAGE, THE GENERATOR SHALL BE SYNCHRONIZED WITH THE 4.16 KV BUS AND THE DIESEL BREAKER MANUALLY CLOSED FROM THE
. ELECTRICAL CONTROL BOARD. THE GENERATOR SHALL THEN I
BE LOADED TO AT LEAST THE CONTINUOUS (2) KW RATING AND RUN FOR AT LEAST 60 MINUTES BEFORE BEING OFF-LOADED AND THE DIESEL BREAKER TRIPPED.
l B. THE AUTO-START INITIATING CIRCUIT FOR EACH DIESEL SHALL l BE TESTED PRIOR TO EACH PLANT STARTUP IF NOT DONE
- DURING THE PREVIOUS WEEK.
l C. TESTS SHALL BE CONDUCTED DURING EACH REFUELING OUTAGE TO DEMONSTRATE THE SATISFACTORY OVERALL AUTOMATIC
', OPERATION OF EACH DIESEL SYSTEM. THIS TEST SHALL BE
! CONDUCTED BY:
j '.
t INITIATION OF A SIMULATED AUTO-START SIGNAL TO VERIFY THAT THE DIESEL STARTS, FOLLOWED BY, f
ii. INITIATION OF A SIMULATED SIMULTANEOUS LOSS OF
4.16KV SUPPLIES TO BUS lA3 (lA4). PROPER OPERATION WILL BE VERIFIED BY OBSERVATION OF:
(1) DE-ENERGIZATION OF BUS 1A3 (lA4).
(2) LOAD SHEDDING FROM BUS (BOTH 4160 V AND 480 V).
(3) ENERGIZATION OF BUS 1A3 (lA4) .
(4) AUTOMATIC SEQUENCE START OF EMERGENCY LOAD, AND (5) OPERATION FOR 2 5 MINUTES WHILE ITS GENERATOR IS LOADED WITH THE EMERGENCY LOADS.
[EL. VERIFICATION THAT EMERGENCY LOADS DO NOT EXCEED THE 2000-HR KW RATING OF THE ENGINE.00 D. MANUAL CONTROL OF DIESEL GENERATORS AND BREAKERS SHALL ALSO BE VERIFIED DURING REFUELING SHUTDOWNS.
E. EACH DIESEL GENERATOR SHALL BE GIVEN A THOROUGH INSPECTION ON A REFUELING (R) FREQUENCY IN ACCORDANCE ,
WITH THE MANUFACTURER'S RECOMMENDATIONS FOR THIS CLASS OF STANDBY SERVICE.+ , - y ,. ,
F. THE FUEL OIL TRANSFER PUMPS SHALL BE VERIFIED TO BE OPERABLE EACH MONTH.
' "TiiZ ABOVE IESTC WILL SC CONCIOCREO SATI5 FACTORY T FDm
?.PPLICALLE ZGUlemrru OrwAIE5 as DESIONEO.[TMS- iiILL
[-HieLUDE CALInD"IOP OF MONI"ORINC INCTRUMENTATION
^
s
30 SURVEILLANCE REQUIREMENTS O
V 3.7 Emergency Power System Periodic Tests (Continued)
Basis The emergency power system provides power requirements for the en-gineered safety features in the event of a DBA. Each of the two diesel generators is capable of supplying minimum required safety feature equipment from independent buses. This redundancy is a factor in establishing testing intervals. The monthly tests specified vill demonstrate operability and load capacity of each diesel generator.
The fuel supply and various controls are continuously monitored and alarmed for off-normal conditions. At approximately yearly intervals g (during refueling shutdowns) automatic starting on loss of off-site l power and automatic load shedding, diesel connection, and loading vill be verified. At the same intervals, capability will be verified for manual e:nergency control of these functions from the diesel and switch-gear rooms.
Considering system redundancy, the specified testing intervals for the station batteries should be adequate to detect and correct any malfunction before it can result in system malfunction. Batteries vill deteriorate with time, but precipitous failure is extremely unlikely. The surveillance specified is that which has been de-monstrated over the years to provide an indication of a cell becoming unserviceable long before it fails.
References J
m unn , um wu i . a . , . c. .
(2) /SAR, Section 8.h.1 (3) */SAR, Section 8.3.h (h) "/SAR, Section 8.h.2 7 hese 4e si s are conducfed lo meef NRC Qcneric l~efley Th e. cbffives c.f he issue of reduc 4iens in 84 cold
- i s fast reg 6+ar a.edi ng +f s . f:'o r thi s r
+he 4est verifying o. to second s:a.e4 unit be conducted feorn ambienf Conclib once per #84 dogs for each diesel.
Other- mon +hly fests w(ll o.ito u3 k r-rna n &cture recommended wa, m .up %
uduce 4he enechan ica ( dress and - o n
-'s O +"a>--i -
3-60 AmendmentNo.k
~
DISCUSSION. JUSTIFICATION. AND SIGNIFICANT HAZARDS CONSIDERATIONS The NRC's Generic Letter 84-15, dated July 2,1984, provided staff objectives with respect to the emergency diesel generators at nuclear power facilities.
The first attachment to this letter addressed a staff objective of reducing the number of cold fast start surveillance tests for diesel generators which were deemed as resulting in premature diesel engine degradation. The Generic Letter requested a description of the current surveillance testing program, and a description of intended actions to reduce cold fast starts.
OPPD's response directly applicable to this item of the Generic Letter was provided in our letter LIC-84-413, dated December 28, 1984. In this letter, we described our cold fast start surveillance testing program, and stated that we would conduct a review of the Technical Specifications and surveil-lance testing in order to determine if any unnecessary testing could be eliminated. In a letter to the NRC (LIC-85-362) dated October 25, 1985, OPPD stated that our review indicated that certain changes to the Technical Speci-fications would be in order. We further noted that we expected to submit those changes in the form of an Application for Amendment approximately 30 days after full power operation following the 1985 refueling and maintenance outage. Accordingly, OPPD submitted an Application for Amendment in March, 1986, which proposed changes to the Technical Specifications to meet that objective.
Subsequent to our initial Application for Amendment of Operating License, several discussions concerning that Application have been held with the NRC reviewer.
Several comments were raised which have been discussed with the plant staff and the reviewer. As was noted to the reviewer, the changes requested must be concurred with by both the Fort Calhoun Station Plant Review Committee, and the Omaha Public Power District offsite Safety Audit and Review Commit-tee. The following discussion presents our revised changes to the Technical Specifications and amplified discussion of the justification for those changes.
Technical Specification 2.4. Limitino Condition for Operation of the Containment Coolina System. (2). Modification of Minimum Reouirements.
Technical Specification 2.4 currently allows modification of the minimum requirements of the specification for the Containment Cooling System during power operation to allow a total of two of the components listed in Technical Specification 2.4 a. and b. to be inoperable at any one time (in addition to one raw water pump) provided that the emergency diesel generator connected to the other engineered safeguards 4.16 KV bus (1A4 or 1A3) is started to demonstrate operability.
The proposed Technical Specification removes the requirement for the emergency diesel to be started in order to modify the minimum requirements.
This particular requirement imposes the stresses associated with cold fast starts on the diesel engines. Additionally, the requirement in the existing Technical Specifications is inconsistent with the Standard Technical Specifi-cations, in that no such diesel start is imposed by the Standard Technical ATTACHMENT B
Attachment B (continued)
Specifications in order to comply with the provisiona of the Limiting Conditions for Operation for the Containment Cooling System. Therefore, OPPD believes that there exists adequate justification for deletion of the requirement to start the diesel engine, and has therefore proposed that the Limiting Condition for Operation be revised to remove that requirement.
(This item remains as it was initially submitted in our March 21, 1986, submittal.) Additionally, the BASIS to Technical Specification 2.4 has been revised in order to provide consistency between specification and basis.
(This item was overlooked in our initial application.)
Technical Specification 3.1, Instrumentation and Control.
This Technical Specification refers to the requirements for the surveillance testing in terms of checks, calibration, and testing of the Reactor Protective System (RPS) found in Table 3-1, Engineered Safety Features (ESF) found in Table 3-2, and other miscellaneous plant instrumentation and controls found in Table 3-3.
Table 3-2, item 11 currently addresses several surveillance requirements associated with the diesel generators. Additionally, other testing require-ments are specified in Technical Specification 3.7. The reasons for removing Item 11 from the Table wem discussed with the reviewer. He believed it was appropriate to only maintain items in Table 3-2 which directly relate to diesel circuitry, but not the engine. The reviewer requested that the ch a k of the diesel start circuit be retained in Table, while diesel starts be moved to Technical Specification 3.7. However, all tests presented in Table 3-2 Item 11, result in a diesel start, and, as such will be placed in Technical Specification 3.7. This information was verbally agreed to by the reviewer. This is consistent with Standard Technical Specifications. The following explains the rationale for each of the changes made to Table 3-2.
Item lla of the existing Specifications contains requirements to perform monthly testing of the diesel by manual initiation of a starting signal.
This requirement relates to more than the diesel circuitry, and has been moved to Specification 3.7. Additionally, the monthly testing of the diesel is specified in greater detail, including the necessary starting signals, and acceptance criteria, in Specification 3.7. Therefore, Item lla has been moved to Specification 3.7 to avoid duplication.
Item 11b as it exists in Table 3-2 has been factored into Technical Specifi-cation 3.7(1)c, as was discussed with the reviewer. The start of the diesel engine upon a Safety Injection Signal will be reserved for the refueling test specified in Technical Specification 3.7(1)c and discussed below. This proposed change will reduce the potential for error during the conduct of surveillance by keeping the amount of activity associated with the Safety Injection Actuation Signal test to a minimum. Therefore, the requirements of item lib have been revised and moved to 3.7(1)c.
Attachment B (continued)
The requirement of Table 3-2, Item lle (to perform a test of the diesel during refueling shutdowns) is redundant to the tests which are specified in the proposed revision to 3.7(1)c. Therefore, the requirement of llc has been removed from the table. The test is specified in greater detail, including initiating parameters and acceptance criteria, in Specification 3.7, and is better placed there. The requirement remains the same as is detailed below.
The requirements of Table 3-2, Item lid (to test the diesel auto start initiating circuits prior to startup if not done during the previous week) have been moved to Specification 3.7(1)b. The test results in a diesel engine start and should be located with the other diesel tests in Specification 3.7.
Technical Specification 3.7, Emergency Power System Periodic Tests.
Technical Specification 3.7(1)a has been modified to allow for the diesel start (10 seconds) from ambient conditions to be performed at least once per 184 days. The other engine starts, conducted at least once per 31 days, in this Specification will be allowed to be preceded by an engine pre-lube period and/or other warmup procedures recommended by the manufacturer so that mechanical stress and wear on the engine is minimized. This is consistent with the changes recommended in Generic Letter 84-15. The format is slightly different. (That is, the 184 day Specification is not contained in a footnote; it has been included in the text of the Specification.)
As noted above, Table 3-2, Item lid, has been moved to Item 3.7(1)b.
Specification 3.7(1)c has been reworded in order to increase its clarity.
No major functional changes between testing currently conducted will result from this change. Technical Specification 3.7(1)e has been altered in wording somewhat and incorporated into Specification 3.7(1)c as a criteria of acceptance of the refueling frequency testing. The initial 0 PPD Application for Amendment of Operating License had proposed removing this particular Specification from the Technical Specifications. OPPD has modified 3.7(1)c to include a verification that the auto-connected loads do not exceed 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of the engine, consistent with Standard Technical Specifications.
The loads which are auto-connected are currently monitored as a part of the refueling test, so it will not result in any additional requirements.
The statement has been reworded to denote an action associated with surveillance rather than the current wording which connotates a design requirement.
The design basis considerations of this requirement are found in USAR Section 8.4.1.2 and are footnoted as such.
The portion of current Technical Specification 3.7(1)c dealing with manual control of the diesel generators and breakers has been separated from the automatic operation portion. Ithasbeendesignatedas3.7(1)d. Current Specification 3.7(1)f has been redesignated as 3.7(1)e. The frequency was changed from annual to Refueling. It is the intention of this change to no longer conduct the manufacturer's recommended overahaul (which requires removing the diesel from service) during power operation. This arrangement was
Attachment B (continued) recommended by the Region IV office.
A note has been added to the Basis section 3.7 to specify that Generic Letter 84-15 recommendations to reduce cold fast starts have been incorporated into these Technical Specifications.
Justifications This change to the Technical Specifications is proposed in response to the NRC recommendations of Generic Letter 84-15 and has been modified per con-versations with the NRC technical reviewer. This change will reduce the number of unnecessary cold fast starts of the emergen:y diesel generators.
These changes will bring applicable portions of the Fort Calhoun Station Technical Specifications into conformance with the recommended changes noted in the Attachment to Enclosure 1 of Generic Letter 84-15.
Significant Hazards Considerations The proposed changes to the Technical Specifications have been assessed against the provisions of 10 CFR 50.92. This review resulted in the following conclusions:
The proposed changes will not involve a significant increase in the probability or consequences of an accident or malfunction of equipment previously evaluated in the Safety Analysis Report. These changes are intended to reduce degrad-ation of the emergency diesel generators caused by cold fast starts. Thus, the probability of malfunction of equipment can be considered to have been lessened. Additionally, by not conducting the annual overhaul during power operation, the possibility of an occurrence at power with one engine tagged out for maintenance is virtually eliminated.
The changes will not involve a significant reduction in a margin of safety.
The changes are intended to provide a less severe method of testing of the diesel generators, thus decreasing the likelihood of degradation and wear.
By restricting the overhaul to refueling outages, the periods of time with one diesel tagged out for maintenance during normal operation will be limited to necessary maintenance concerns, instead of prevention maintenance.
The NRC has provided guidance concering the application of standards for determining whether a significant hazards consideration exists by providing certain examples of amendments that are not likely to involve significant hazards considerations (51 FR 7751). This application is deemed to be similar to example (i) in that it will achieve consistency throughout the
Attachment B (continued) .
Technical Specifications by placing all diesel generator surveillance requirements in one location. This amendment is also somewhat similar to example (iv) where the relief based upon " acceptable operation" is in part based on NRC reassessment of the testing requirements imposed upon diesel generators. Based upon conclusions drawn from Generic Letter 84-15, the proposed changes are in keeping with the concept of increasing safety by precluding unnecessary wear on the emergency diesel engines. For these reasons, OPPD believes that these changes do not constitute a significant hazards consideration.
