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Category:CORRESPONDENCE-LETTERS
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999 Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached ML20217G9261999-10-15015 October 1999 Forwards Insp Rept 50-285/99-10 on 990913-17.One NCV Noted ML20217G2331999-10-14014 October 1999 Forwards Insp Rept 50-285/99-09 on 990913-17.No Violations Noted LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999 Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999 Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls ML20217B5111999-10-0606 October 1999 Forwards Amend 193 to License DPR-40 & Safety Evaluation. Amend Revises TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance require- Ments for RCS Flow Rate ML20216H7231999-09-29029 September 1999 Informs That Util 980325 Response to GL 97-06, Degradation of SG Internals, Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Fort Calhoun Station,Unit 1 ML20212L9571999-09-27027 September 1999 Informs That Follow Up Insp for Drill/Exercise Performance Indicator Will Be Conducted During Wk of 991001 LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999 Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999 Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999 Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999 Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999 Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters IR 05000285/19990081999-09-0707 September 1999 Forwards Insp Rept 50-285/99-08 on 990907-0811.No Violations Noted.Insp Consisted of Exam of Activities Conducted Under License as Relate to Safety & to Compliance with Commission Rules & Regulations & with Conditions of License ML20211P2581999-09-0303 September 1999 Forwards Insp Rept 50-285/99-06 on 990809-12.No Violations Noted.Insp Consisted of Exam of Activities Under License as Related to EP & to Compliance with Commission Rules & Regulations & with Conditions of License LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999 Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase ML20211J9231999-09-0202 September 1999 Forwards SE Accepting Licensee 990301 Requests for Relief Re Third 10-year ISI Interval for Plant,Unit 1.Relief Proposed Alternatives to Requirements in ASME B&PV Section XI,1989 Edition,Paragraphs IWA-5242(a) & IWA-5250(a)(2) ML20211L3241999-09-0202 September 1999 Informs That Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) of Amend 192 to License DPR-40 Issued on 990727.Corrected Page Encl LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999 Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld ML20211F4491999-08-25025 August 1999 Forwards Ltr from Ja Miller,Dtd 990819,which Notified State of Iowa of Deficiency Identified During 990810,Fort Calhoun Station Biennial Exercise.One Deficiency Identified for Not Adequately Demonstrating Organizational Capability LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d) LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999 Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld ML20210R1491999-08-13013 August 1999 Forwards Insp Rept 50-285/99-07 on 990719-23.No Violations Noted.Nrc Identified One Issue Which Was Evaluated Under Risk Significance Determination Process & Was Determined to Be of Low Risk Significance LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N1991999-08-0909 August 1999 Informs That as Result of NRC Review of Licensee Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210P8991999-08-0909 August 1999 Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999 Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999 Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331 LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999 Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program ML20210G1851999-07-27027 July 1999 Forwards Amend 192 to License DPR-40 & Safety Evaluation. Amend Consists of Changes to TS in Response to 990129 Application LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999 Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630 ML20216D6951999-07-26026 July 1999 Informs That During 990614 Review of Fort Calhoun,Nrc Noted That Drill/Exercise Performance Indicator Has Entered White Band,Which Indicated Level of Licensee Performance That Warranted Increased Regulatory Response LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999 Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999 Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld ML20210D9471999-07-22022 July 1999 Forwards Amend 191 to DPR-40 & Safety Evaluation.Amend Authorizes Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20210C0201999-07-20020 July 1999 Informs That Due to Administrative Oversight,Revised TS Bases Provided in to Fort Calhoun Station Were Not Dated.Dated Pages to TS Encl ML20210B0761999-07-19019 July 1999 Forwards Insp Rept 50-285/99-05 on 990601-0710.No Violations Noted ML20209G5351999-07-15015 July 1999 Informs That Staff Incorporated Rev of TS Bases Provided by Licensee Ltr Dtd 980904,into Fort Calhoun Station Tss. Staff Finds Revs to Associated TS Bases to Be Acceptable. Revised Bases Pages Encl ML20209F5741999-07-12012 July 1999 Ack Receipt of Transmitting Exercise Scenario for Upcoming Biennial Offsite Exercise Scheduled 990810.Scenario Reviewed & Acceptable ML20209G5591999-07-0808 July 1999 Forwards Detailed Listing of Staff Concerns with C-E TR NPSD-683,rev 3 & RCS pressure-temperature Limits Rept LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999 Forwards Fort Calhoun Performance Indicators Rept for May 1999 LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999 Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld ML20209D8771999-07-0101 July 1999 Summarizes 990630 Public Meeting Conducted in Fort Calhoun, Ne Re Results of Completed Culture Survey,Plant Status, Facility Activities Re New NRC Oversight Process & License Renewal.Licensee Handout & Attendance List Encl LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999 Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999 Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999 Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999 Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999 Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999 Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999 Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999 Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999 Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999 Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999 Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999 Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d) LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999 Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999 Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331 LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999 Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999 Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999 Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630 LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999 Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999 Forwards Fort Calhoun Performance Indicators Rept for May 1999 LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999 Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999 Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624 LIC-99-0061, Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl1999-06-30030 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl LIC-99-0056, Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-061999-06-22022 June 1999 Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-06 LIC-99-0059, Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning1999-06-22022 June 1999 Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning LIC-99-0054, Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 9908101999-06-0808 June 1999 Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 990810 LIC-99-0052, Forwards Fort Calhoun Station Performance Indicators, for Apr 19991999-06-0202 June 1999 Forwards Fort Calhoun Station Performance Indicators, for Apr 1999 LIC-99-0045, Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl1999-05-26026 May 1999 Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl LIC-99-0046, Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise1999-05-12012 May 1999 Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise LIC-99-0028, Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage1999-04-30030 April 1999 Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage LIC-99-0036, Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F1999-04-28028 April 1999 Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F LIC-99-0043, Forwards Fort Calhoun Performance Indicators Rept for Mar 19991999-04-28028 April 1999 Forwards Fort Calhoun Performance Indicators Rept for Mar 1999 LIC-99-0041, Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager1999-04-27027 April 1999 Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager LIC-99-0037, Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue1999-04-26026 April 1999 Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue LIC-99-0039, Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a1999-04-20020 April 1999 Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a LIC-99-0038, Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl1999-04-20020 April 1999 Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl LIC-99-0033, Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps1999-04-15015 April 1999 Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps LIC-99-0035, Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure1999-04-0808 April 1999 Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure LIC-99-0031, Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate1999-03-31031 March 1999 Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0032, Forwards Fort Calhoun Station Performance Indicators, for Feb 19991999-03-31031 March 1999 Forwards Fort Calhoun Station Performance Indicators, for Feb 1999 LIC-99-0029, Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques1999-03-30030 March 1999 Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques LIC-99-0027, Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld1999-03-16016 March 1999 Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld LIC-99-0022, Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl1999-03-12012 March 1999 Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl LIC-99-0024, Informs That OPPD Withdraws Applications Submitted by 950626 &1999-03-12012 March 1999 Informs That OPPD Withdraws Applications Submitted by 950626 & LIC-99-0016, Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives1999-03-0101 March 1999 Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives LIC-99-0023, Forwards FCS Performance Indicators for Jan 19991999-03-0101 March 1999 Forwards FCS Performance Indicators for Jan 1999 LIC-99-0020, Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included1999-02-24024 February 1999 Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included LIC-99-0011, Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 11999-02-0505 February 1999 Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 1 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARLIC-90-0705, Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl1990-09-17017 September 1990 Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl LIC-90-0745, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions1990-09-17017 September 1990 Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions LIC-90-0717, Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-071990-09-13013 September 1990 Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07 LIC-90-0716, Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls1990-09-13013 September 1990 Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls LIC-90-0740, Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits1990-09-12012 September 1990 Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits LIC-90-0741, Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets1990-09-0707 September 1990 Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets LIC-90-0440, Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes1990-09-0606 September 1990 Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes LIC-90-0667, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 9005291990-09-0404 September 1990 Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 900529 LIC-90-0712, Forwards fitness-for-duty Program Performance Data for Period of Jan-June 19901990-08-31031 August 1990 Forwards fitness-for-duty Program Performance Data for Period of Jan-June 1990 LIC-90-0683, Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations1990-08-27027 August 1990 Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations LIC-90-0627, Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection1990-08-22022 August 1990 Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection LIC-90-0670, Forwards Fort Calhoun Station Performance Indicators for Jul 19901990-08-22022 August 1990 Forwards Fort Calhoun Station Performance Indicators for Jul 1990 LIC-90-0662, Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution1990-08-22022 August 1990 Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution LIC-90-0673, Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl1990-08-22022 August 1990 Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl LIC-90-0636, Forwards Results of 1990 Refueling Outage Inservice Insp & Rept for Repairs or Replacement1990-08-13013 August 1990 Forwards Results of 1990 Refueling Outage Inservice Insp & Rept for Repairs or Replacement LIC-90-0591, Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-21990-08-13013 August 1990 Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-2 LIC-90-0631, Responds to Generic Ltr 89-15 Re NRC Solicitation of Utils to Voluntarily Participate Emergency Response Data Sys Program.Util Prepared to Work W/Nrc to Investigate Actions Necessary to Implement Program at Plant1990-08-0808 August 1990 Responds to Generic Ltr 89-15 Re NRC Solicitation of Utils to Voluntarily Participate Emergency Response Data Sys Program.Util Prepared to Work W/Nrc to Investigate Actions Necessary to Implement Program at Plant LIC-90-0485, Confirms Interim Resolution of Identified Problem Associated W/Use of Input Variable for PORV Opening Time in Calculation of Low Temp Overpressure Protection Sys Setpoints1990-08-0707 August 1990 Confirms Interim Resolution of Identified Problem Associated W/Use of Input Variable for PORV Opening Time in Calculation of Low Temp Overpressure Protection Sys Setpoints LIC-90-0645, Forwards Application for Amend to License DPR-40,making Typo & Administrative Corrections to Tech Specs1990-08-0202 August 1990 Forwards Application for Amend to License DPR-40,making Typo & Administrative Corrections to Tech Specs LIC-90-0647, Informs That Tl Patterson Assumed Position of Plant Manager, Effective 9008011990-08-0101 August 1990 Informs That Tl Patterson Assumed Position of Plant Manager, Effective 900801 LIC-90-0659, Advises of Plans to Achieve Operability of Third Auxiliary Feedwater Pump by 9008101990-07-31031 July 1990 Advises of Plans to Achieve Operability of Third Auxiliary Feedwater Pump by 900810 LIC-90-0449, Forwards Rev 1 to EA-FC-90-037, Control Room Habitability Evaluation for NUREG-0737,Item III.D.3.41990-07-20020 July 1990 Forwards Rev 1 to EA-FC-90-037, Control Room Habitability Evaluation for NUREG-0737,Item III.D.3.4 LIC-90-0588, Provides Notification of SPDS Implementation at Plant,Per1990-07-19019 July 1990 Provides Notification of SPDS Implementation at Plant,Per LIC-90-0585, Forwards Simulator Malfunction Cause & Effects1990-07-18018 July 1990 Forwards Simulator Malfunction Cause & Effects ML20055D9351990-07-0202 July 1990 Forwards Fort Calhoun Station Performance Indicators,May 1990 LIC-90-0564, Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility1990-06-29029 June 1990 Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility LIC-90-0522, Forwards Revised Response to Notice of Deviation from Insp Rept 50-285/90-02.Corrective Actions:Cable Trays 5-4A & 5-4B Reworked to Neatly Tie Down Cables & Remove Crossovers & Engineering Instruction GEI-9 on Electrical Sys Updated1990-06-29029 June 1990 Forwards Revised Response to Notice of Deviation from Insp Rept 50-285/90-02.Corrective Actions:Cable Trays 5-4A & 5-4B Reworked to Neatly Tie Down Cables & Remove Crossovers & Engineering Instruction GEI-9 on Electrical Sys Updated LIC-90-0566, Forwards 1990/1991 Statement of Cash Flow from Operations. Cash Flow Statement Deviates from Reg Guide 9.4 Due to Util Being Political Subdivision of State of Ne1990-06-29029 June 1990 Forwards 1990/1991 Statement of Cash Flow from Operations. Cash Flow Statement Deviates from Reg Guide 9.4 Due to Util Being Political Subdivision of State of Ne LIC-90-0488, Responds to Request for Info Re Status of Implementation of Generic Safety Issue Requirements1990-06-29029 June 1990 Responds to Request for Info Re Status of Implementation of Generic Safety Issue Requirements LIC-90-0446, Forwards Application for Amend to License DPR-40,to Restrict Containment Spray Use as Backup for Shutdown Cooling in Tech Specs1990-06-28028 June 1990 Forwards Application for Amend to License DPR-40,to Restrict Containment Spray Use as Backup for Shutdown Cooling in Tech Specs LIC-90-0429, Forwards Application to Amend License DPR-40,adding Hydrogen Purge Sys to Tech Spec.Discussion,Justification & NSHC Analysis for Amend,Provided1990-06-28028 June 1990 Forwards Application to Amend License DPR-40,adding Hydrogen Purge Sys to Tech Spec.Discussion,Justification & NSHC Analysis for Amend,Provided ML20043J0611990-06-22022 June 1990 Responds to NRC 900523 Ltr Re Violations Noted in Insp Rept 50-285/90-29.Corrective Actions:Five Chemistry Technicians Provided Refresher Training on 900427 on Existing EPIP-EOF-6 ML20044A1631990-06-22022 June 1990 Requests That NRC Continue Processing Exemption Request for Configuration of wide-range Nuclear Instrumentation Cables in Fire Area 34B (Upper Electrical Penetration Room). Emergency Boration Added to Achieve Safe Shutdown ML20044A4961990-06-18018 June 1990 Forwards Supplemental Application for Amend to License DPR-40,making Administrative Corrections to Tech Specs. Procedure SO-G-70, Chemical Control Also Encl ML20043G2981990-06-14014 June 1990 Provides Followup to Special Rept on Inoperable Fire Barriers.Eight Inoperable Dampers Replaced Under Mod MR-FC-87-036, Fire Damper Replacement. Remaining 38 Dampers Found to Be Acceptable After Damper Design Review ML20043E6451990-06-0808 June 1990 Provides Supplemental Response to Generic Ltr 88-17 & NRC Bulletin 80-12.Plant Pumps & Suction Header Piping Not Originally Constructed for Use as Backup to LPSI Sys for Shutdown Cooling ML20043E0071990-06-0101 June 1990 Discusses Rev to Previous Commitments Made in Response to Requirements of 10CFR50,App R,Section Iii.G Re post-fire Repairs to Equipment Required for Cold Shutdown Following Fire in Fire Area 6 ML20043G3281990-06-0101 June 1990 Advises That Personnel at Util Reviewed Reactor Operator Licensing Exam Administered on 900529.Comments on Exam Encl ML20043C1811990-05-29029 May 1990 Advises That Util Has Cleaned RW HXs AC-1A & AC-1D & Will Clean AC-1C by 900615 ML20043B4981990-05-24024 May 1990 Updates Schedule for Submitting Results of PORV Block Valve Prototype Testing.Establishment of Test Parameters & Development of Test Procedures Tentatively Scheduled for Submittal in Nov 1990.Final Rept Expected by 910630 ML20043B5061990-05-23023 May 1990 Advises That Testing to Verify Operability of Hydrogen Purge Sys Successfully Completed During 1990 Refueling Outage.Proposed Tech Spec Rev Will Be Submitted by 900701 ML20043B4731990-05-23023 May 1990 Forwards Fort Calhoun Station Performance Indicators, Monthly Rept for Apr 1990 ML20043A7821990-05-18018 May 1990 Advises That Licensee Plans to Replace Valves HCV-247 & HCV-2988 During 1991 Refueling Outage Pending Successful Redesign & Retesting of New Valves by Valcor ML20043A8021990-05-18018 May 1990 Advises That Walkdown of safety-related Portions of Plant to Verify Accuracy of Fire Barrier Penetration Drawings & Surveillance Tests Will Be Completed by 900831 ML20043B0391990-05-16016 May 1990 Informs of Current Status of Post Accident Sampling Sys. Program Meets Min Requirements & Fulfills Conditions of Tech Spec 5.15 ML20042G9861990-05-11011 May 1990 Forwards Rev 0 to Interim Operability Criteria (Ioc) Criteria for Performing Safety Analysis for Interim Operability of Piping, Resulting from Discussion at 900306 & 0418 Meetings ML20042G9571990-05-10010 May 1990 Forwards Suppl to Application for Amend to License DPR-40, Making Administrative Clarification to Chloride Sampling Requirements.Standing Order Procedure S.O.-M-10, Tool Accountability Also Encl ML20042G9981990-05-10010 May 1990 Forwards Proprietary & Nonproprietary Rev 13 to EPIP-EOF-18, Offsite Radiological Surveys. ML20042H0021990-05-10010 May 1990 Fowards Fort Calhoun Station Performance Indicators,Mar 1990, Monthly Rept ML20042G4671990-05-0909 May 1990 Forwards Application for Amend to License DPR-40,changing Chemical & Vol Control Sys 1990-09-07
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Cmaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402/536-4000 y._ ...a ;
March 18, 1988 J' j LIC-88-191 t% 4 b M [ih uj 1 !R Mr. Robert D. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Tx. 76011
Reference:
- 1. Docket No. 50-285
- 2. Enforcement Conference held March 15, 1988, Arlington, Texas
Dear Mr. Martin:
SUBJECT:
Fire Protection Enforcement Conference of March 15, 1988 0maha Public Power District (0 PPD) appreciates the time and attention given by you and your staff to the OPPD Fire Protection conference of March 15, 1988.
Thi:: letter is a restatement of commitments made by 0 PPD to you during the course of the conference.
OPPD will continue hourly fire watch patrols at Fort Calhoun Station until identified openings inside conduit are sealed in accordance with the draft criteria presented at the conference. This effort is currently in progress and completion is expected by the end of March 1988. Any openings inside conduit which are not sealed will be evaluated for adequacy by a fire protection engineer. This analysis will be maintained on file by 0 PPD and will be completed by the end of May 1988.
In addition, OPPD will update and clarify its commitment on this issue, including an association with the utility group currently addressing this issue. OPPD will submit this clarification to the NRC by the end of April 1988.
This letter also transmits to you a set of the overheads utilized by 0 PPD during the conference. Proprietary information from Professional loss Control (PLC) has been removed from this set.
8804110200 000310 PDR ADOCK 05000205 q DCD \ \
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.. o R."D. Martin iTC-88-191 Page 2 If you have any questions, please do not hesitate to contact us.
Sincerely, R. L. Andrews Division Manager Nuclear Production RLA/me cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Ave., N.W.
Washington, DC 20036 R. 3. Martin, NRC Regional Administrator A. Bournia, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector 4
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NRC FIRE PROTECTION MEETING AGENDA MARCH 15, 1988 OPENING REMARKS / INTRODUCTION: R.L. ANDREWS OVERVIEW OF MEETING: J.J. FISICARO IMMEDIATE ACTIONS TAKEN/RESULTS ACHIEVED: J.E. LECHNER
- FIRE WATCH PATROL
- DETERMINATION OF IMMEDIATE SAFETY SIGNIFICANCE
- WALKDOWN
! - SEALING OF CONDUITS
- COMPLIANCE WITH TECH. SPEC. COMMITMENTS REVIEW OF OPPD' S FIRE PROTECTION COMMITMENTS: S.K. GAMBHIR
- BRANCH TECHNICAL POSITION 9.5.1, APP.A l
l
- OCTOBER 1978 SUBMITTAL
- FIRE PROTECTION SER DATED NOVEMBER 1980 l - RE-CONSTITUTION OF CONDUIT SEALING CRITERIA
- COMPLIANCE WITH SER COMMITMENTS
- RE-EVALUATION OF SEALING CRITERIA (PER GENERIC LETTER 86-10)
TOPICAL REPORT ON TESTING OF CONDUIT SEALS MIKE MOWRER CORRECTIVE ACTIONS / FUTURE UPGRADES: J.E. LECHNER
- EXCELLENCE IN OPERATION REVIEW l - REVISED FIRE HAZARD ANALYSIS 1
l SAFETY SIGNIFICANCE T.L. PATTERSON l
CLOSING STATEMENT AND CONCLUSIONS P.L. ANDREWS t l . . _ _ __ .____ _ __
N .
N N .
- : REQUIRED :
= l 3 HR "
! ! BARRIER \!
SWITCHGEAR j i SWITCHGEAR i i ROOM i.
ROOM i.
i A : B :
- 4.. 4.. : 4.. 4.. :
l CONDUIT CONDUIT l CONDUIT CONDUIT i BATTERY !
BATTERY !
i ROOM :
ROOM :
, i A : B :
p E
a m a n u m m e s m o s a m m e n e n e et e e a e e a s o m w a s e a m a n u s e.
SWITCHGEAR/ BATTERY ROOM PHYSICAL LAYOUT
BTP APCSB 9.51 APPESDLX A AUGUST 23, 1976 PAGES 15 A:SD 16 APPLICATI0ft DOCKETED BUT C0tlSTRUCTI0fl PLAtlTS UtlDER C0tlSTRUCTI0ft At10 PER!ilT tt0T RECE1VED AS OF 7/1/76 OPERATIllG PLAttlS (j) Floors, wall and ceilings enclos- (j) SAliE. The fire hazard in each ing separate fire areas should area should be evaluated to have minimum fire rating of three determine barrier requirements.
hours. Penetrations in these fire If barrier fire resistance can-barriers, including conduits and not be made adequate, fire piping, should be sealed or closed detection and suppression to provide a fit esistance rat- should be provided, such as:
ing at least eva to that of the fire barrier itself. Door open- (i) water curtain in case of ings should be protected with fire, equivalent rated doors, frames and hardware that have been tested and (ii) flame retardant 7 approved by a nationally recog- coatings, nized laboratory. Such doors should be normally closed and (iii) additional fire locked or alarmed with alarm and barriera, annunciation in the control room.
Penetrations for ventitation sys-tem should be protected by a stan-dard "fire door damper" where required. (Refer to NFPA 80, "Fire Doors and Windows.")
l
O, .
REVIEW
~
STANDARD
~
PLAN 9.5.1
- SUREG 75 / 087 REV 1 A:S D 2 (3) Cable and cable tray penetration of fire barriers (vertical and horizontal) should be sealed to give protection at least equivalent to that required for the fire barrier. The design of fire barrier pene horizontal and vertical cable trays should be qualified by tests.grations for The pene-tration qualification tests should use the time-temperature exposure curve specified by ASTM E-119, "Fire Test of Building Construction and Materials."
Openings inside conduit larger than four inches in diameter should be sealed at the fire barrier penetration; these seals should be qualified by tests as descrioed above. Openings inside conduit four inches or less in diameter should be sealed at the fire barrier and should be qualified by tests as described above unless the conduit extends at least five feet on each side of the fire barrier and is sealed either at both ends or at the fire barrier with noncombustible material to prevent the passage of smoke and hot gases. Fire barrier penetrations that must maintain environmental isolation or pressure differentials should be qualified by test to maintain the barrier integrity under the conditions specified above.
- 3. Plants for which (a) CP applications were docketed prior to, but were not issued a CP, by July 1, 1976; or (b) construction permits or operating licenses were issued prior to July 1,1976, should follow the guidelines of either (a)
Appendix A (dated August 23, 1976 to BTP APCSB 9.5-1; dated May 1, 1976; or (c) this position.
PAGES 29 AND 46
CHEMTROL PROGRAM -
OPPD SUBMITTAL DATED OCTOBER 18, 1978 6.0 Other Small Openinas Certain openings in small conduits, small gaps, and small repairs are to be accomplished by utilizing U.L. listed and fire-rated silicone caulk sealants. (See CHEMTROL Specification Hos. 3440 and 3450).
7.0 Larce Openinos 7.1 Where larger penetration openings do not economically permit the entire volume of the opening to be sealed with expanded silicone elastomeric foam (refer to Item 2.0, Work Scope, as contained herein), Applicator is to provide FIREWALL sprayed on, fast-cure fiberglass reinforced cementitious matrix to thickness as specified.
Densities e cum
.80 gm/cm 3 (50 lbs./ft.groduct
) to 2.0shah bg (125 gm/cm as selecW lbs./ft. ig) ranges fmm (Refer to CHEMTROL Specification No. 4000.)
PAGE 2.02
SER DATED -
=
NOVEMBER 17, 1980 Item 3.1.20 - Cable Penetration Seals SER Section 3.1.20 indicates that the licensee will upgrade the electrical cable penetration scals to a design demonstrated by test to have a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire resistance rating.
By letter dated October 18, 1978, the licensee described the proposed modifica-tions to achieve the 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire resistance rating. The licensee also indi-cated that penetration seals being installed have passed tests conducted generally in agreement with the methods and criteria described in the flRC August 30, 1977 letter to the Omaha Public Power District, except that no pressure differential was applied across the seals during the test.
The licensee stated that Chemtron Corporation, to whose installation procedures fort Calhoun cable penetration seals have been installed, acknowledged that a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire test was successfully conducted with a positive pressure of 9.0 inches of water maintained on a 5,885 square inch penetration.
Because the largest penetration in the plant is 1,924 square inches, and because the maximum expected nonfire differential pressure is approximately 0.5 inches of water, we find the proposed modifications fer cable penetration seals satisfactory and consider this item to be closed.
PAGE 5
RE CONSTITUTION OF CONDUIT SEALING CRITERIA BACKGROUND
- NO PROBLEM WITH EXTERNAL SEALING
- NO PROBLEM WITH SEALING OF " SLEEVES"
- NRC CRITERIA FOR SEALING INSIDE OF CONDUITS WAS NOT CLEAR - (1978 TIME FRAME)
- NO INDUSTRY GUIDANCE WAS AVAILABLE CRITERIA USED IN 1978 SEALED PER CHEMTROL PROCEDURE (OCT, 1978 SUBMITTAL) waw h &
'# SEAL IF e < 10'
- e =l SLEEVES f SEALED AT PENETRATION g l
SUBSEQUENT REVISIONS
- THE CRITERIA WAS REVISED TO REQUIRE SEALING FOR CONDUITS > 2" IF e < 5' -0" ( MP-FP-2) l
\
1 l
1
COMPLIANCE WITH SER COMMITMENTS (PARAGRAPH 6.0 OF 1978 SUBMITTAL) -
- NO SPECIFIC COMMITMENTS WERE INTENDED TO SEAL INSIDE OF ALL CONDUITS
- PARAGRAPH 6.0 ( PAGE 2.02) WAS INTENDED AS MATERIAL SPECIFICATION - NOT AN INSTALLATION SPECIFICATION.
(REFERENCE - PROMATEC LETTER)
- CRITERIA WAS DISCUSSED WITH AMERICAN NUCLEAR INSURERS (ANI) (REFERENCE - TELECON WITH ANI AND JOE ALDERI)
- CONSISTENT WITH INDUSTRY PRACTICE (1978-1980)
- GOOD FAITH EFFORT TO COMPLY WITH REQUIREMENTS ASAP
ORIGIN AL DOCUMENT ILLEGlBLE RETYPED FOR CLARITY 3-14-88 ORIGINAL INCLUDED FOR INFORMATION NEXT PAGE 4
i To whom it may concern:
This information is provided regarding penetration seals for Fort Calhoun Power Station.
I was the cognizant engineer responsible for the sealing of. penetration seals.
During the course of the effort a question arose concerning sealing of opened ended conduits. Note: As a matter of course all conduits which acted as a sleeve (e.g. penetration wall then went in tray) were sealed.
Since all of our seals / seal designs were/had to be approved by ANI (the authority having jurisdiction), the question was asked when would an opened ended conduit not require a seal. The response was >10'. There was no other issues regarding the sealing of conduits (i.e., conduit systems were not traced to 'a n elbow or condulet, opened and scaled, only ooened ended conduits were sealed.
Respectfully, 1-i Joseph M. Aldieri 3/11/88 l
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RECORD OF TFlf PH0flE COMMUNICATI0ft M . R . 110. FC-77 15 FILE NO. GSE.FCl-79-782 DATE: 10/24/79 TIME: 1ELEPH0tlE NO. 87-36 PARTY CALLING: JOSEPH M. ALDIERI OPPD-GSE (fW1E) (COMPAf4Y)
PARTY ANSWERING: WAYflE HOLMES AMERICAf1 NUCLEAR INSURERS (fWlE) (COMPAtlY)
SUBJECT:
FIRE SEALS IN CONDUIT TELEC0ft
SUMMARY
(Including Decisions and Commitments)
I asked Wayne, if he was aware of any requirements relative to acceptance critaria for conduit runs, which did not terminate at the fire barrier. (i.e.,
extended a certain distance beyond the fire barrier).
Wayne stated that there wasn't any.
I noted that various "rules of thumb" have been established ind considered them only as "nice to do item" since they are not based on any test data.
He agreed.
I asked if we were to pack mineral wool around the ends of such conduit runs, would it be considered as a fire barrier.
Wayne said no.
ORIGir4 AL DOCUMEt4T ILLEGIDLE RETYPED FOR CLARITY 3-14-88 ORIGIN AL litCLUDED FOR ltJFORMAT10tl t1 EXT PAGE bThbbhEbbihEb Forward information to J. Connolley DISTRIBUTION CGK, JMA, SKG, JEC, (FC)
GSE- A-1-4 for a Rev. 8/85
PRC Minutes February 2, 1980 Page Two I_T_D_4, AC"r10'i Procedure Changes PRC Reviewed the following Proced.ar-CIDGED 5229 (ST-Co.Yf-7) 5228 (ST-CO.';T-~'
5218 (SP-ICI-1) 5227 (S.O. T-1M 5230 (MP-RC-6-6-1A) 5194 (DCR 78-50/SRDC0 79-80) 5139 (MR-FC-78-56/SRDC0 79-73) e Final Review of:
5219 (MP-RC-6-1) 5186 (MP-VA-3) 5189 (SRDC0 79-80) 5162 (SRDC0 79-80)
Telecon between J. Alderi and PRC Reviewed and concurs with telecon.
Wayne Holmes of American Nuclear Insurers concerning Fire Seals in Conduit dated 10-24-79 CLOGG Letter to PRC concerning PRC Reviewed and approved per letter Cancellation of SP-RCS-6 FC-131-80.
concerning RCP Motor 011 Collection System Fabrication Control CIASE PRC Subcommittee concerning PRC Reviewed and approved per letter Repiscenent of Main Steam Line PC-126-SO.
Penetration Bellows MR-FC-78-2.
CIASED Letter from Chen Nuclear concern- PRC Reviewed per letter dated 1-25 80.
ing Barnwell Disposal Site Burial Space Allocation Revisions.
CIDSED
'IMI-2 Task Force Meeting Minutes PRC Reviewed and any open items placed 1-29-80. on Open Item Checklist.
CtD3D Inster from CSE concerning PRC Reviewed per letter TC-80-59.
Inspection of Safety Related Piping Inside Containment in /
reference NRC I.E. Bulletin 79-1k. S /
CIAS E ,
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b4 41toGLI55M MATIAJALS AND itOiNOLOGIES. INC.
March 11, 1988 Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102 Attention: Mr. Stanley R. Crites Nuclear Engineering
- Generating Station Engineering
Subject:
Request for Clarification
Dear Mr. Crites:
This in to confirm our telephone conversation this dato regarding work which I was involved in as the Project Manager for Chomtrol corporation for Omaha Pub-lic Power District at the Fort calhoun Nucioar Power Station. This work took place during the period of September through Decc=bor of 1978.
To the best of my recollection, Paragraph 6.0 of chemtrol's Guido Specifica-tion for Design FC225 is a natorial spocification, and should not be con-sidered as an installation specification. The cephasis of this ite:n is placed on the natorial being UL listed, and has nothing to do with the type of opening that the asterial is utili:cd to seal. J Regarding the original contract scopo (portaining to open ended conduit termi-nations), Mr. Joe Aldori, Project Engineer at that poricxi of timo for OPPD.
and (as Project Manager for Cheatrol corporation), did discuss the issue of conduits, that were cemented in place in firo walls, which terminated within ten feet of the fire barrier vall. I recall that Mr. Alderi directed us to provide a nilicone foam seal in such conduits which ter=inated within tea feet of the fire barrior vall. The seal design utilised vould have been the Same design for a three hour firo rated coal; however, it would have been installed at the point of termination, and only on the side of the wall, where the con-duit terminated within ten feet of the fire barrior. It was censidered that any before conduits that ran a distance greator than ten foot from the fire t>strier terminating were rogarded as continuous run conduit and, ao such, were not scaled. As regards blockout openings in the control Room floor, thesc openings were sealed as per tested design as a fire seal, and cable and/or conduit, which penetrated the opening, vore considered merely to bo penetra-ting of theclements.
blockout, However, if the conduit terminated within the slab, at the top an appropriate fire coal design was installed, at that point of conduit the blockout.
termination, just as if it were part of the continu:us opening of l
M nmr P.O. BOX 472
- HOUSTON. TEXA5 m13 o aim m on i WN'i
9I Oiaaha Public Power District March 11, 1988 Page 2 Aside from these cases, I do not recall any other situations ir. which internal conduit mentation. seals were specifically identified in the work scope or quality docu-In the case of open ended conduits, which terminated less than ten feet from the fire barrier (that were sealed),
installed it is probable that the seals far the purposes of invoicing.were recorded as a penetration seal, from a quality st I hope this information assists your efforts. If I can provide any further information or clarification, feel free to contact me.
Sincerely, PROMATEC E. L. Brault Vice President ELasbe v
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RE EVALUATION OF SEALING CRITERIA
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( GENERIC LETTER 86 10 )
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component under consideration is capable of performing its intended function y during and after the postulated fire, as needed. Licensees seeking exemptions 4 from Section III.G.2 must show that the alternative proposed provides -
reasonable assurance that this criterion is met. (Note also that Section III.G.2 applies only to equipment needed for hot shutdown. Therefore, an exemption from III.G.2 for cold shutdown equipment is not needed. The tem "damage by fire" also includes damage to equipment from the nomal or J.
inadvertent operation of fire suppression systems.
- 4. Fire Area Boundaries The tem "fire area" as used in Appendix R means an area sufficiently bounded a to withstand the hazards associated with the area and, as necessary, to '
l orntact im.nortant eonioment within the area from a fire outside the area. In order te meet the rag;.htSn, fire area bcun:icrius need ran be completely ~
sealed floor-to-ceiling, wall-to-wall boundaries. However, all unsealed openings should be identified and considered the evaluatino the effectiveness.
of the overall barrier. I Where fire area boundaries are not wall-to-wall, floor-to-ceiling boundaries with all penetrations scaled to the fire rating ,
required of the boundaries, licensees must perfom an evaluation to assess the adequacy of fire boundaries in their plants to determine if the boundaries will withstand the hazards associated with the area. This analysis must be performed by at least a fire protection engineer and, if required, a systems engineer. Althouoh not rewired, licensees may submit their evaluations for staff review and concurrence. However, if certain cable penetrations were
- identified as open SER items at the time Appendix R became effective,Section III.M of the rule applies (see 10 CFR 50.48(b)), and any variation from *he
- ! requirements of Section III.M requires an exemption. In any event, the analyses must be retained by the licensees for subsequent NRC audits.
- 5. Automatic Detection and Suppression Sections III.G.2.b and III.G.2.c of Appendix R state that "In addition, fire detectors and automatic fire suppression system shall be installed in the fire area..." Other provisions of Appendix R also use the phrase "fire detectors and an automatic fire suppression system in the fire area..." (see e.g.,
SectionIII.G.2.e).
i l In order to comply with these provisions, suppression and detection sufficient to protect against the hazards of the area must be installed. In this regard, detection and suppression providing less than full area coverage may be adecuate to comoly with the regulation. Where full area suppression and detection is not installed, licensees must perfom an evaluation to assess the adequacy of partial suppression and detection to protect against the hazards in the area. The evaluation must be performed by a fire protection engineer and, if required, a systems engineer. Although not required, licensees may submit their evaluations to the staff for review and concurrence. In any event, the evaluations must be retained for subsequent NRC audits. Where a licensee is providing no suppression or detection, and exemption must be requested.
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1.0 PtRPOSE The purpose of this document is to establish a technically based policy ,
regarding internal fire sealings of electrical conduits penetrating fire barriers at the Fort Calhoun Station.
2.0 BACKGROUND
The Fort Calhoun Station committed to APCSB 9.5-1, Appendix A, 'Overall Requirements of Nuclear Plant Fire Protection Program." The guidance established in 9.5-1 Appendix A in paragraph D.1.(j) states: ,
(j) "Floors, valls, and ceilings enclosing separate fire areas should have a minimum fire rating of thrco hours.
Penetrations in these fire barricrs, including conduits and piping, should be sealed or closed to provide a firo resistance rating at least equal to that of the fire barrict itself . . ."
and in paragraph D.3.(d) states:
"(d) cable and Cable tray penetration of fire barriers l (vertical and horizontal) should be sealed to give pro-tection at least equivalent to that fire barrier. The design of fire barriers for horizontal and vertical cable trays should, as a minimum, meet the require =ents of ASTM E-119, "Fire Test of Building Construction and Materials," including the hos'c strou test."
Neither of these references are specific to internal sealing of :en-I duits.
i The CMEB 9.5-1 (NUitEG 0800) in paragraph 5.a.(3) referenc'es internal sealing of conduits as follows:
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"(3) openings through fire barriers for pipe, conduit, and cable trays which separate fire areas should be sealed or closed to provide a fire resistance rating at least equal to that required of the barrier itacif.
Openings insido conduit larger than 4 inches in dia=eter should be scaled at the fire barrier penetration. Open-ings inside conduit 4 inches or less in dia:eter should l
I be sealed at the fire barrier unless the conduit extends '
at lea::t 5 feet on each sido of the fire barrier and is
! sealed either at both ends or at the fire barrier vith
' noncombustible caterials to prevent the passage of s=oke and hot gases . . ."
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,l., a The policy applied at Fort Calhoun Station is stated in MP-PP-2, Appen-dix B, paragraph C.3. Type D:
"Inside of conduits with a required minimum depth of RTV foam of 7 inches.
NOTE: Type D seals only applicable to 2" or larger conduits which do not extend 5 feet into the Fire Area on one side."
Subsequent to the establishment of this policy, additional technical information in the form of a fire test was developed by a group of utilities. Based on this test data, Fort Calhoun Station should change its policy regarding internal sealing of conduits as outlined in Sec .
tion 4.0 below.
3.0 RRFERENCES ,
3.1 Appendix A to Branch Technical Position APCSB 9.5-1 "Guidelines for Fire Protection for Nuclear Power Plants Docketed prior to July 1, 1976" Rev. 1, Nover.ber 18, 1976.
g 3.2 Branch Technical Position'CMES 9.5-1 "Guidelines for Fire Protec-tion for Nuclear Power Plants" Rev. 2, July, 1981.
3.3 Omaha Public Pover District, Fort Calhoun Station, Unit 1, Fire Hasards Analysis (updated) Rev. O, October 12, 1987.
3.4 Port Calhoun Station Unit No. 1, Maintenance Procedure HP-PP-2 Fire Barrier Penetration Seals.
3.5 Conduit Fire Protection Research Program, Final Report, . Profes-sional Loss control, Inc., June 1,'1987.
4.0 POLTCT The purpese of'a flee barrier is to prevcat the spread of a fire"from
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'orie side of the barrier to the other. Openings in the barrier must be prot'ected to the level ..necessary to prevent fire propagation. The design objective for conduit penetrations as with door openings, duct
- penetrations and cable tray penetrations is to prevent the spread of fire through the barrier.
open conduits that terminate n the vall should be treated as sleeves and should be sealed with rated scals as described MP FP 2. Cencral
! policy for sealing of other conduits penetrating fire barriers to pre-vent the propagation of fire is outlined belov.
Conduits that terminate in junction boxes or other nonco:nbustible t
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closure need no additional sealing. Conduits that run through an area but do not terminate in that area need not La scaled in that area.
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- 2. Open conduits smaller than 2" diameter that terminate I foot or greater from tbc barrier need not be scaled.
- 3. Open conduits of 2" diameter that terminate 3 feet or greater from the barrier need not be scaled.
- 4. Open conduits of greater than 2" in diameter that terminate 3 feet or greater from the barrier and have a cable fill of 40% or greater need not be scaled.
These scaling requirements for open conduits can be summarized in the following table.
Ooon Termination Distance (ft)
Conduit Diameter (in) <1' 11' 21'
<2" Y N N 2" Y Y N
>2" Y Y Y(I)
(1) NOTE: only if conduit cable fill density is <40%
When sealing of conduits, other than sleeves, is required, the seal may be a plug of ceramic fiber and need not be applied at the vall but at the open end of the conduit.
5.0 JUSTIFICATION These design guidelines are based on the conduit seal fire test con-ducted on November 13, 1986, at Construction Technology Laboratories (See Reference 3.5). The test slab incorporated 101 conduit penetra-tions of diameters from 1/2" through 2,", projecting from l' through 7' outside the furnace. The test slab vas exposed to the ASTM E.119 atan-dard fire exposure for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. During the test, no flames propagated through the conduits and no cables vere ignited on the unexposed side of the test slab. Only one conduit (a 2" open conduit with 10% cable fill, terminating 1 foot from the slab) exceeded 7000F at its end.
Open conduits larger than 2" diameter vere not tested, but internal temperature measurements vere madeT3", 4", and 6" conduit. Based on these internal temperatures, it can be concluded that conduits larger than 2" diameter which terminate 3' or greater from the barrier and vhich have a cable fill density of 40% or greater need not be scaled.
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- TOPICAL REPORT ON '
l TESTING OF l CONDUIT SEALS t
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PURPOSE OF CONDUIT SEAL TESTS e CONDUCTED IN RESPONSE TO DIFFERING REGULATORY GUIDANCE (BTP 9.5-1 8 APPENDIX A, APPENDlX R, 8 NUREG 0800) .
e COST EFFECTIVE FIRE PROTECTION CONCERNS FOR INSTALLATION a SURVEILLANCE e ESTABLISH TECHNICAL BASIS FOR TYPE OF SEALS l
NOTE: 26 UTILITIES ORIGINALLY PARTICIPATED IN 11/86 l
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- . 0 f. CO N DU::~ S ~? ES~ EJ TEST PARAMETERS: '
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- DISTANCE OF CONDUIT TERMINATION l
FROM BARRIER
- TYPE OF CONDUIT TERMINATION
.__.__._.,,,.__._ _ _ _. __,,, , _ _ _ , . _ , _ . _ . ,.___.,__w,m.-,.. _ . - - --
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These sealing requirements for open conduits can be summarized in the k following table. y 8
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - - - _ _ _ _ _ _ _ _ _ - _ - - - _ _ _ _ _ - _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ n Open Termination Distance (ft) @
Cenduit Diameter (in) <1' 11' 23' f
<2" Y N N .
2" .Y Y N $
>2" Y Y Y(I) s 8
(1) NOTE: only if conduit cable. fill density is <40% y When sealing of conduits, other than sleeves, is required, the seal any be a plug of ceramic fiber and need not be applied at the vall but at the open end of the conduit.
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LANJARY 22 - M3:1JA1Y 10, .988
" TO ASSESS TiiE ADEQUACY OF TliE FORT CAlliOUN FIRE PROTECTION PROGRAM IN LIGliT OF CURRENT REGULATORY PHILOSOPliY WITil TliE INTENTION OF BEING AN INDUSTRY STANDARD BEARER IN TliE FIELD OF NUCLEAR POWER PLANT FIRE PROTECTION."
TliE ULTIMATE G0AL: TO AClllEVE AND MAINTAIN A SALP RATING 0F "1" IN Tile AREA 0F FIRE PROTECTION
. . . := . .g na. ,. .. . . . .
REVISED FIRE HAZARD ANALYSIS 1
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EGEA"01Y 10CI1m"S E"17m !
APCSB 9.5-1 Appendix A ASB 9.5- 1 -
NUREG 0800 10 CFR 50 Appendix R Generic Letter 81-12 Generic Letter 86-10 1.E. NOTICE 84-09 I SECY 85-306 l
NRC INSPECTION MODULES (various applicable) !
NRC SALP REPORTS since 1981 NFPA CODES (various applicable) ;
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