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MONTHYEARML20050B8331982-04-0202 April 1982 Forwards Addl Info Re Environ Qualification of Equipment Installed in Response to TMI Requirements,Including Revision to Page 2 of 810826 Qualification Package Encl 13,per 820201 Commitment Project stage: Request ML20062B7271982-07-23023 July 1982 Forwards Safety Evaluation Identifying Three Open Items Re App J Containment Leak Testing Review.Nrc Review Put on Hold Pending Receipt of Licensee Info.Response Due in 30 Days. Supplemental SER Will Be Issued Upon Review Completion Project stage: Approval ML20062B7301982-07-23023 July 1982 Safety Evaluation Re App J Review.Three Open Items Identified Project stage: Approval ML20064N4571982-09-0303 September 1982 Responds to Open Items Identified in NRC 820723 Safety Evaluation Re Containment Leakage Testing Program.Resolution of Areas of Containment Personnel Access Door Seal & Isolation Valve Testing to Be Provided by 821101 Project stage: Other ML20065A5581982-09-0707 September 1982 Advises That Revised Electrical Equipment Qualification Manual Will Be Issued within Next 2 Months Project stage: Request ML20066E5771982-11-0505 November 1982 Forwards Addl Info Re Containment Leakage Testing Program, in Response to Open Items Identified in NRC . Penetration M-44 Will Be Tested Per 10CFR50 App J.Util Amend Application Will Be Revised Project stage: Other ML20066B9531982-11-0505 November 1982 Forwards Electrical Equipment Qualification Manual Per IE Bulletin 79-01B, Environ Qualification of Safety-Related Electrical Equipment Project stage: Request ML20070U2931983-01-26026 January 1983 Proposed Tech Spec Rev Incorporating Type C Testing of Penetration M-44 & Calculating Max Allowable Leakage Rate Using 0.2% by Weight of Containment Atmosphere Per 24 H at 60 Psig Project stage: Other ML20070U2791983-01-26026 January 1983 Application to Amend OL Revising App J Tech Specs to Incorporate Type C Testing of Penetration M-44 & Calculate Max Allowable Leakage Rate Using 0.2% by Weight of Containment Atmosphere Per 24 H at 60 Psig Project stage: Request ML20137D8141985-08-0101 August 1985 Notice of Environ Assessment & Finding of No Significant Impact Re Util 830126 Request for Exemptions from Section III of 10CFR50,App J Project stage: Other ML20137D8001985-08-0101 August 1985 Forwards Notice of Environ Assessment & Finding of No Significant Impact Re 830126 Request for Exemption from 10CFR50,App J Project stage: Approval ML20137V9551985-11-27027 November 1985 Withdraws 830126 & 0902 Applications for Amends to License DPR-40,changing Allowable Containment DBA Leak Rate to 0.2% by Weight Per Day.Tech Spec Section 3.5 Resubmitted,Per 770330 Application for Amend Project stage: Request ML20137V9881985-11-27027 November 1985 Tech Spec Section 3.5, Containment Test, Maintaining Max Allowable Containment Leak Rate at 0.2% by Weight Per Day Project stage: Other ML20137H5531986-01-10010 January 1986 Exemption from Requirements of 10CFR50,App J Re Primary Reactor Containment Leakage Testing for water-cooled Power Reactors Project stage: Approval ML20137H5361986-01-10010 January 1986 Forwards Exemption from Certain Requirements of App J to 10CFR50 & SER Re Primary Reactor Containment Leakage Testing for water-cooled Power Reactors.Review of Proposed Tech Spec Changes Continuing Project stage: Approval ML20151Y6941986-02-0303 February 1986 Safety Evaluation Supporting Amend 95 to License DPR-40 Project stage: Approval ML20151Y6781986-02-0303 February 1986 Amend 95 to License DPR-40,revising Surveillance Tech Specs to Ensure That Reactor Containment Bldg Leak Rate Testing Performed Per 10CFR50,App J Project stage: Other ML20151Y6671986-02-0303 February 1986 Forwards Amend 95 to License DPR-40 & Safety Evaluation. Amend Revises Surveillance Tech Specs to Ensure That Reactor Containment Bldg Leak Rate Testing Performed Per 10CFR50,App J Project stage: Approval ML20211B1351986-06-0303 June 1986 Safety Evaluation Supporting Amend 97 to License DPR-40 Project stage: Approval ML20211B1231986-06-0303 June 1986 Amend 97 to License DPR-40,transferring Recirculation Heat Removal Sys Surveillance Requirements from Containment Test Part of Tech Specs to New Tech Spec Section Project stage: Other ML20211B0951986-06-0303 June 1986 Forwards Amend 97 to License DPR-40 & Safety Evaluation. Amend Transfers Recirculation Heat Removal Sys Surveillance Requirements from Containment Test Part of Tech Specs to New Tech Spec Section Project stage: Approval 1983-01-26
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Category:CORRESPONDENCE-LETTERS
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999 Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached ML20217G9261999-10-15015 October 1999 Forwards Insp Rept 50-285/99-10 on 990913-17.One NCV Noted ML20217G2331999-10-14014 October 1999 Forwards Insp Rept 50-285/99-09 on 990913-17.No Violations Noted LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999 Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999 Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls ML20217B5111999-10-0606 October 1999 Forwards Amend 193 to License DPR-40 & Safety Evaluation. Amend Revises TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance require- Ments for RCS Flow Rate ML20216H7231999-09-29029 September 1999 Informs That Util 980325 Response to GL 97-06, Degradation of SG Internals, Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Fort Calhoun Station,Unit 1 ML20212L9571999-09-27027 September 1999 Informs That Follow Up Insp for Drill/Exercise Performance Indicator Will Be Conducted During Wk of 991001 LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999 Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999 Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999 Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999 Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999 Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters IR 05000285/19990081999-09-0707 September 1999 Forwards Insp Rept 50-285/99-08 on 990907-0811.No Violations Noted.Insp Consisted of Exam of Activities Conducted Under License as Relate to Safety & to Compliance with Commission Rules & Regulations & with Conditions of License ML20211P2581999-09-0303 September 1999 Forwards Insp Rept 50-285/99-06 on 990809-12.No Violations Noted.Insp Consisted of Exam of Activities Under License as Related to EP & to Compliance with Commission Rules & Regulations & with Conditions of License LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999 Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase ML20211J9231999-09-0202 September 1999 Forwards SE Accepting Licensee 990301 Requests for Relief Re Third 10-year ISI Interval for Plant,Unit 1.Relief Proposed Alternatives to Requirements in ASME B&PV Section XI,1989 Edition,Paragraphs IWA-5242(a) & IWA-5250(a)(2) ML20211L3241999-09-0202 September 1999 Informs That Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) of Amend 192 to License DPR-40 Issued on 990727.Corrected Page Encl LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999 Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld ML20211F4491999-08-25025 August 1999 Forwards Ltr from Ja Miller,Dtd 990819,which Notified State of Iowa of Deficiency Identified During 990810,Fort Calhoun Station Biennial Exercise.One Deficiency Identified for Not Adequately Demonstrating Organizational Capability LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d) LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999 Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld ML20210R1491999-08-13013 August 1999 Forwards Insp Rept 50-285/99-07 on 990719-23.No Violations Noted.Nrc Identified One Issue Which Was Evaluated Under Risk Significance Determination Process & Was Determined to Be of Low Risk Significance LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N1991999-08-0909 August 1999 Informs That as Result of NRC Review of Licensee Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210P8991999-08-0909 August 1999 Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999 Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999 Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331 LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999 Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program ML20210G1851999-07-27027 July 1999 Forwards Amend 192 to License DPR-40 & Safety Evaluation. Amend Consists of Changes to TS in Response to 990129 Application LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999 Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630 ML20216D6951999-07-26026 July 1999 Informs That During 990614 Review of Fort Calhoun,Nrc Noted That Drill/Exercise Performance Indicator Has Entered White Band,Which Indicated Level of Licensee Performance That Warranted Increased Regulatory Response LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999 Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999 Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld ML20210D9471999-07-22022 July 1999 Forwards Amend 191 to DPR-40 & Safety Evaluation.Amend Authorizes Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20210C0201999-07-20020 July 1999 Informs That Due to Administrative Oversight,Revised TS Bases Provided in to Fort Calhoun Station Were Not Dated.Dated Pages to TS Encl ML20210B0761999-07-19019 July 1999 Forwards Insp Rept 50-285/99-05 on 990601-0710.No Violations Noted ML20209G5351999-07-15015 July 1999 Informs That Staff Incorporated Rev of TS Bases Provided by Licensee Ltr Dtd 980904,into Fort Calhoun Station Tss. Staff Finds Revs to Associated TS Bases to Be Acceptable. Revised Bases Pages Encl ML20209F5741999-07-12012 July 1999 Ack Receipt of Transmitting Exercise Scenario for Upcoming Biennial Offsite Exercise Scheduled 990810.Scenario Reviewed & Acceptable ML20209G5591999-07-0808 July 1999 Forwards Detailed Listing of Staff Concerns with C-E TR NPSD-683,rev 3 & RCS pressure-temperature Limits Rept LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999 Forwards Fort Calhoun Performance Indicators Rept for May 1999 LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999 Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld ML20209D8771999-07-0101 July 1999 Summarizes 990630 Public Meeting Conducted in Fort Calhoun, Ne Re Results of Completed Culture Survey,Plant Status, Facility Activities Re New NRC Oversight Process & License Renewal.Licensee Handout & Attendance List Encl LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999 Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999 Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999 Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999 Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999 Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999 Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999 Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999 Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999 Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999 Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999 Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999 Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d) LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999 Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999 Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331 LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999 Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999 Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999 Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630 LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999 Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999 Forwards Fort Calhoun Performance Indicators Rept for May 1999 LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999 Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999 Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624 LIC-99-0061, Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl1999-06-30030 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl LIC-99-0056, Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-061999-06-22022 June 1999 Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-06 LIC-99-0059, Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning1999-06-22022 June 1999 Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning LIC-99-0054, Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 9908101999-06-0808 June 1999 Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 990810 LIC-99-0052, Forwards Fort Calhoun Station Performance Indicators, for Apr 19991999-06-0202 June 1999 Forwards Fort Calhoun Station Performance Indicators, for Apr 1999 LIC-99-0045, Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl1999-05-26026 May 1999 Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl LIC-99-0046, Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise1999-05-12012 May 1999 Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise LIC-99-0028, Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage1999-04-30030 April 1999 Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage LIC-99-0036, Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F1999-04-28028 April 1999 Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F LIC-99-0043, Forwards Fort Calhoun Performance Indicators Rept for Mar 19991999-04-28028 April 1999 Forwards Fort Calhoun Performance Indicators Rept for Mar 1999 LIC-99-0041, Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager1999-04-27027 April 1999 Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager LIC-99-0037, Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue1999-04-26026 April 1999 Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue LIC-99-0039, Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a1999-04-20020 April 1999 Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a LIC-99-0038, Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl1999-04-20020 April 1999 Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl LIC-99-0033, Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps1999-04-15015 April 1999 Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps LIC-99-0035, Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure1999-04-0808 April 1999 Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure LIC-99-0031, Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate1999-03-31031 March 1999 Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0032, Forwards Fort Calhoun Station Performance Indicators, for Feb 19991999-03-31031 March 1999 Forwards Fort Calhoun Station Performance Indicators, for Feb 1999 LIC-99-0029, Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques1999-03-30030 March 1999 Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques LIC-99-0027, Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld1999-03-16016 March 1999 Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld LIC-99-0022, Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl1999-03-12012 March 1999 Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl LIC-99-0024, Informs That OPPD Withdraws Applications Submitted by 950626 &1999-03-12012 March 1999 Informs That OPPD Withdraws Applications Submitted by 950626 & LIC-99-0016, Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives1999-03-0101 March 1999 Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives LIC-99-0023, Forwards FCS Performance Indicators for Jan 19991999-03-0101 March 1999 Forwards FCS Performance Indicators for Jan 1999 LIC-99-0020, Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included1999-02-24024 February 1999 Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included LIC-99-0011, Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 11999-02-0505 February 1999 Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 1 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARLIC-90-0705, Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl1990-09-17017 September 1990 Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl LIC-90-0745, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions1990-09-17017 September 1990 Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions LIC-90-0717, Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-071990-09-13013 September 1990 Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07 LIC-90-0716, Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls1990-09-13013 September 1990 Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls LIC-90-0740, Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits1990-09-12012 September 1990 Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits LIC-90-0741, Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets1990-09-0707 September 1990 Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets LIC-90-0440, Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes1990-09-0606 September 1990 Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes LIC-90-0667, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 9005291990-09-0404 September 1990 Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 900529 LIC-90-0712, Forwards fitness-for-duty Program Performance Data for Period of Jan-June 19901990-08-31031 August 1990 Forwards fitness-for-duty Program Performance Data for Period of Jan-June 1990 LIC-90-0683, Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations1990-08-27027 August 1990 Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations LIC-90-0627, Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection1990-08-22022 August 1990 Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection LIC-90-0670, Forwards Fort Calhoun Station Performance Indicators for Jul 19901990-08-22022 August 1990 Forwards Fort Calhoun Station Performance Indicators for Jul 1990 LIC-90-0662, Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution1990-08-22022 August 1990 Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution LIC-90-0673, Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl1990-08-22022 August 1990 Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl LIC-90-0636, Forwards Results of 1990 Refueling Outage Inservice Insp & Rept for Repairs or Replacement1990-08-13013 August 1990 Forwards Results of 1990 Refueling Outage Inservice Insp & Rept for Repairs or Replacement LIC-90-0591, Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-21990-08-13013 August 1990 Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-2 LIC-90-0631, Responds to Generic Ltr 89-15 Re NRC Solicitation of Utils to Voluntarily Participate Emergency Response Data Sys Program.Util Prepared to Work W/Nrc to Investigate Actions Necessary to Implement Program at Plant1990-08-0808 August 1990 Responds to Generic Ltr 89-15 Re NRC Solicitation of Utils to Voluntarily Participate Emergency Response Data Sys Program.Util Prepared to Work W/Nrc to Investigate Actions Necessary to Implement Program at Plant LIC-90-0485, Confirms Interim Resolution of Identified Problem Associated W/Use of Input Variable for PORV Opening Time in Calculation of Low Temp Overpressure Protection Sys Setpoints1990-08-0707 August 1990 Confirms Interim Resolution of Identified Problem Associated W/Use of Input Variable for PORV Opening Time in Calculation of Low Temp Overpressure Protection Sys Setpoints LIC-90-0645, Forwards Application for Amend to License DPR-40,making Typo & Administrative Corrections to Tech Specs1990-08-0202 August 1990 Forwards Application for Amend to License DPR-40,making Typo & Administrative Corrections to Tech Specs LIC-90-0647, Informs That Tl Patterson Assumed Position of Plant Manager, Effective 9008011990-08-0101 August 1990 Informs That Tl Patterson Assumed Position of Plant Manager, Effective 900801 LIC-90-0659, Advises of Plans to Achieve Operability of Third Auxiliary Feedwater Pump by 9008101990-07-31031 July 1990 Advises of Plans to Achieve Operability of Third Auxiliary Feedwater Pump by 900810 LIC-90-0449, Forwards Rev 1 to EA-FC-90-037, Control Room Habitability Evaluation for NUREG-0737,Item III.D.3.41990-07-20020 July 1990 Forwards Rev 1 to EA-FC-90-037, Control Room Habitability Evaluation for NUREG-0737,Item III.D.3.4 LIC-90-0588, Provides Notification of SPDS Implementation at Plant,Per1990-07-19019 July 1990 Provides Notification of SPDS Implementation at Plant,Per LIC-90-0585, Forwards Simulator Malfunction Cause & Effects1990-07-18018 July 1990 Forwards Simulator Malfunction Cause & Effects ML20055D9351990-07-0202 July 1990 Forwards Fort Calhoun Station Performance Indicators,May 1990 LIC-90-0564, Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility1990-06-29029 June 1990 Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility LIC-90-0522, Forwards Revised Response to Notice of Deviation from Insp Rept 50-285/90-02.Corrective Actions:Cable Trays 5-4A & 5-4B Reworked to Neatly Tie Down Cables & Remove Crossovers & Engineering Instruction GEI-9 on Electrical Sys Updated1990-06-29029 June 1990 Forwards Revised Response to Notice of Deviation from Insp Rept 50-285/90-02.Corrective Actions:Cable Trays 5-4A & 5-4B Reworked to Neatly Tie Down Cables & Remove Crossovers & Engineering Instruction GEI-9 on Electrical Sys Updated LIC-90-0566, Forwards 1990/1991 Statement of Cash Flow from Operations. Cash Flow Statement Deviates from Reg Guide 9.4 Due to Util Being Political Subdivision of State of Ne1990-06-29029 June 1990 Forwards 1990/1991 Statement of Cash Flow from Operations. Cash Flow Statement Deviates from Reg Guide 9.4 Due to Util Being Political Subdivision of State of Ne LIC-90-0488, Responds to Request for Info Re Status of Implementation of Generic Safety Issue Requirements1990-06-29029 June 1990 Responds to Request for Info Re Status of Implementation of Generic Safety Issue Requirements LIC-90-0446, Forwards Application for Amend to License DPR-40,to Restrict Containment Spray Use as Backup for Shutdown Cooling in Tech Specs1990-06-28028 June 1990 Forwards Application for Amend to License DPR-40,to Restrict Containment Spray Use as Backup for Shutdown Cooling in Tech Specs LIC-90-0429, Forwards Application to Amend License DPR-40,adding Hydrogen Purge Sys to Tech Spec.Discussion,Justification & NSHC Analysis for Amend,Provided1990-06-28028 June 1990 Forwards Application to Amend License DPR-40,adding Hydrogen Purge Sys to Tech Spec.Discussion,Justification & NSHC Analysis for Amend,Provided ML20043J0611990-06-22022 June 1990 Responds to NRC 900523 Ltr Re Violations Noted in Insp Rept 50-285/90-29.Corrective Actions:Five Chemistry Technicians Provided Refresher Training on 900427 on Existing EPIP-EOF-6 ML20044A1631990-06-22022 June 1990 Requests That NRC Continue Processing Exemption Request for Configuration of wide-range Nuclear Instrumentation Cables in Fire Area 34B (Upper Electrical Penetration Room). Emergency Boration Added to Achieve Safe Shutdown ML20044A4961990-06-18018 June 1990 Forwards Supplemental Application for Amend to License DPR-40,making Administrative Corrections to Tech Specs. Procedure SO-G-70, Chemical Control Also Encl ML20043G2981990-06-14014 June 1990 Provides Followup to Special Rept on Inoperable Fire Barriers.Eight Inoperable Dampers Replaced Under Mod MR-FC-87-036, Fire Damper Replacement. Remaining 38 Dampers Found to Be Acceptable After Damper Design Review ML20043E6451990-06-0808 June 1990 Provides Supplemental Response to Generic Ltr 88-17 & NRC Bulletin 80-12.Plant Pumps & Suction Header Piping Not Originally Constructed for Use as Backup to LPSI Sys for Shutdown Cooling ML20043E0071990-06-0101 June 1990 Discusses Rev to Previous Commitments Made in Response to Requirements of 10CFR50,App R,Section Iii.G Re post-fire Repairs to Equipment Required for Cold Shutdown Following Fire in Fire Area 6 ML20043G3281990-06-0101 June 1990 Advises That Personnel at Util Reviewed Reactor Operator Licensing Exam Administered on 900529.Comments on Exam Encl ML20043C1811990-05-29029 May 1990 Advises That Util Has Cleaned RW HXs AC-1A & AC-1D & Will Clean AC-1C by 900615 ML20043B4981990-05-24024 May 1990 Updates Schedule for Submitting Results of PORV Block Valve Prototype Testing.Establishment of Test Parameters & Development of Test Procedures Tentatively Scheduled for Submittal in Nov 1990.Final Rept Expected by 910630 ML20043B5061990-05-23023 May 1990 Advises That Testing to Verify Operability of Hydrogen Purge Sys Successfully Completed During 1990 Refueling Outage.Proposed Tech Spec Rev Will Be Submitted by 900701 ML20043B4731990-05-23023 May 1990 Forwards Fort Calhoun Station Performance Indicators, Monthly Rept for Apr 1990 ML20043A7821990-05-18018 May 1990 Advises That Licensee Plans to Replace Valves HCV-247 & HCV-2988 During 1991 Refueling Outage Pending Successful Redesign & Retesting of New Valves by Valcor ML20043A8021990-05-18018 May 1990 Advises That Walkdown of safety-related Portions of Plant to Verify Accuracy of Fire Barrier Penetration Drawings & Surveillance Tests Will Be Completed by 900831 ML20043B0391990-05-16016 May 1990 Informs of Current Status of Post Accident Sampling Sys. Program Meets Min Requirements & Fulfills Conditions of Tech Spec 5.15 ML20042G9861990-05-11011 May 1990 Forwards Rev 0 to Interim Operability Criteria (Ioc) Criteria for Performing Safety Analysis for Interim Operability of Piping, Resulting from Discussion at 900306 & 0418 Meetings ML20042G9571990-05-10010 May 1990 Forwards Suppl to Application for Amend to License DPR-40, Making Administrative Clarification to Chloride Sampling Requirements.Standing Order Procedure S.O.-M-10, Tool Accountability Also Encl ML20042G9981990-05-10010 May 1990 Forwards Proprietary & Nonproprietary Rev 13 to EPIP-EOF-18, Offsite Radiological Surveys. ML20042H0021990-05-10010 May 1990 Fowards Fort Calhoun Station Performance Indicators,Mar 1990, Monthly Rept ML20042G4671990-05-0909 May 1990 Forwards Application for Amend to License DPR-40,changing Chemical & Vol Control Sys 1990-09-07
[Table view] |
Text
r _
s =c Omaha Public Power District .
1623 HARNEY 8 O M A H A, esEBRASMA 68102 8 TELEPHONE 536 4000 AREA CODE 402 April 2,1982 LIC-82-143 m o QN Mr. Robert A. Clark, Chief CECMTD U. S. Nuclear Regulatory Commission - -
Office of Nuclear Reactor Regulation 9
, "APR S 198 N
- N Division of Licensing -
Operating Reactors Branch No. 3 E T*[$"":a f Washington, D.C. 20555 h, W I
Reference:
Docket No. 50-285 ~_
Dear Mr. Clark:
Subject:
Environmental Qualification of Equipment Installed in Response to TMI Requirements Omaha Public Power District's letter to the Commission dated February 1, 1982 stated that additional information on the subject issue would be provided within sixty (60) days. The additional information is attached.
An update on other open issues on TMI equipment is included. Also included is a revised page 2 of Enclosure 13 of the District's quali-fication package. Enclosure 13 was revised to indicate that the Dis-trict is presently verifying the documentation of qualification values for 100 day doses to the new accident monitoring equipment. The attached SCEWS and revised Enclosure 13 should be incorporated into the District's qualification package transmitted to the Commission by letter dated August 26, 1981. ,
Sincerely,
/
W. C.
Y0^
nes J
Divisi h Manager Product' ion Operations Attachments
! cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
l Washington, D.C. 20036 t ,
fo4+
69 8204070465 820402 PDR ADOCK 05000 P
t 8 ENCLOSURE OUTSTANDING EQUIPMENT QUALIFICATION INFORMATION FROM DISTRICT'S LETTER DATED FEBRUARY 1, 1982 Cable and Splices Used With TMI Modifications The qualification documentation for the Raychem splices that were used in these TMI Action Item modifications is complete. The inter-connecting cables that were used in these TMI Action Item modifications are CQE qualified cables, as specified by Class 1E equipment qualifi-cation (IEEE Standard 323-1974 and IEEE Standard 383). The SCEWS for both cables and splices are attached.
Auxiliary Feedwater Modifications The qualification documentation for the Foxboro transmitters has not been supplied by the vendor as of yet. When the test results are obtained, the SCEWS will be submitted. The qualification documentation for the ASCO solenoids is complete and the SCEWS are included with this letter. The qualification documentation for the Namco limit switches is complete. The SCEWS are included with this letter.
Reactor Coolant System Vents Modification The SCEWS for the Target Rock solenoid valves used in this modifi-cation was previously submitted. The SCEWS for the Conax penetrations will be providad by May 1,1982, as detailed in the District's letter dated March 25, 1982.
Accident Monitoring Instrumentation The SCEWS and a copy of the test document for the Comsip hydrogen analyzer are complete and included with this letter.
The qualification testing documentation is complete and on file at the Fort Calhoun Station for the Valcor isolation valves used in this accident monitoring instrumentation modification. The qualification testing meets the requirements of IEEE 323-1974. The SCEWS will be submitted by May 1, 1982.
The SCEWS for the ASCO solenoids are complete and included with this letter.
The SCEWS for the Victorcen high range containment radiation area monitor is complete and included with this letter.
l Pressurizer Level Indication j The qualification documentation for the Foxboro transmitters has not been supplied by the vendor as of yet. When the test results are obtained, the SCEWS will be submitted.
I
Containment Sump Water Level Modification The qualification documentation for the GEMS transmitters has not been completed by the test facility. Wyle Labs is in the process of completing final documentation and once obtained by the District the SCEWS will be provided. -
Containment Wide Range Pressure Monitor The containment pressure monitor uses the same Foxboro transmitter discussed above for pressurizer level and auxiliary feedwater modifi-cations. SCEWS will be provided once the District rec"ives the test documentation.
Safety Injection Pump Leakage Detection Syst,:qn The SI pump leakage detection system uses the same GEMS transmitters as the containment sump level indicator; therefore, the same information as discussed above applies.
1 O
e +
' Enclosure 13 Outstanding Items (Continued)
.l
- 10. The District plans ?.o complete testing of the Fisher 304 limit switch by June 30, 1982.
11.* The limit switches $nd Valcor solenoid valves in containment were replaced with environmentally qualified components during the 1981 refueling outage.
12.* The solenoid valves and limit switches in the auxiliary building were replaced with environmentally qualified components during the 1981 refueling outage.
- 13. TE 866 and TE 867 will be replaced during the first refueling outage after receipt of qualified parts.
- 14. Qualified Safety Related Equipment will be identified and marked with orange in the control room and operator training will be completed by June 30, 1982.
- 15. Conax Corporation has verified that the concentration of boron used in the chemical concentration qualification of their Conax seals was an acceptable 3000 parts per million. Conax Corporation has also confirmed in the same letter that their seals are qualified for a design life of 40 years (reference Conax letter from W. C.
Frederick to R. F. Mehaffey (OPPD) dated February 5,1982). The SCEWS have been revised to refle:.t this information and will be provided to the Commission by May 1, 1982.
- 16. The District is in the process of verifying the 100 day dose qualification documentation for accident monitoring modification items.
- These items are complete.
Fccility: Fcrt Calbrun 1 .
Dock:t No.: 50-285 S-200 -
SYSTEM COMPONENT EVALUATON WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTANP CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation system: Containment Hydrogen Operating 100 days P( st Purge System Time Note 1 Accident 1 3 Type Test NONE Item No.: VA-81A & VA-81B Tempera-ture *F N/A N/A N/A N/A N/A NONE ,
Component: Hydrogen Analyzers Pressure PSIg N/A N/A N/A N/A N/A NONE Manufacturer: COMSIP Relative Model No.: Delphi IV Hydrogen Humidity % N/A N/A N/A N/A N/A NONE Analyzer Function: Containment Atmosphere . Chemical f
Hydrogen Analyzers Spray N/A N/A N/A j N/A N/A NONE cn h; Accuracy - Spec: Note 2 Note 3 '- '
'i Demon: Radiation 5 8x10 R 1x106R '
2 3 Type Test NONE Service: Determine % H2 con-concentration in containment Location: Roor 59 Aging N/A 5-10 yrs' N/A 3 Type Test NONE ,
ilooo Level Elev: N/A Submer- Type Test Above' Flood Level: Yes No gence N/A N/A N/A N/A N/A NONE!
Dacumenta'tlon
References:
Notes:
- 1) NUREG 0737. 1) Required to operate during and 100 days after DBA
,, 2) " Implementation hethods and Schedules for 2) IE Bulletin 79-01B submittal Enclosure #12 NURES 0578" Section 2.1.6B page 18, figure 3) See Enclosure 13, Item 16
~
u, 4.2-3 (December 1979) -
- 3 3) COMSIP, Inc. " Test Report IEEE-323-1974
- Qualification of Delphi IV Hydrogen /A'nalyzer j, ., ,
l#)os .
[ .Piesent Qualification
~
.s.
IEEE 323-1974 ,
1 I
4574/b-8/s ,
l
, Facility: Tert Calh:un 1 ,
i
- Dock t N3.
- 50-285 , ,
C-26J - i SYSTcM COMPONENT EVALUATON WORK SHEET )
o c
- .DOCUMENTATON REF. QUALIFI- OUTSTAND
'J - CATION ING fj. , EQUIPMENT DESCRIPTION Specifi- Qualif ' Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation system: . containment Hydrogen Operating -
Type Test Analyzer System Time Note l' Note 3 2 3 NONE Item No.: HCV-883C, 883D, 883E, '
883F, S83G, 883H, HCV-820C, 820D Tempera- ,
820E, 820F,'820G, 820H ture *F 305*F 346*F 1 3 Type Test NONE ,
Component: . Electric Solenoid vv ressure PSIg 60 PSIg 110 PSIg i 3 Type Test NONE Manufacturer: ASCO ,
Relative Model No.: .X206-381-6RF Humidity % 100% ,100% 1 3 Type Test NONE r
Function:' H 2 Analyzer. con- Chemical 1700 ppm 3000 ppm l tainment sample valve. Spray Boron Boron PH 10 1 3 Type Test NONE cn ~.
h2 Accuracy Spec: N/A Note 4 -
l j3 Demon: 'N/A- Radiation 1.6x.10,7R ,
2x10 8R N/A -3 Type Test, NONE
~
Service:
Type Test Location: Containment Aging N/A 10 yr N/A 3 NONE 11000 Level Elev: 1001.0' Submer-Above Flood Level. Yes gence N/A N/A N/A N/A N/A NONE vocumentation xeterences: Notes:
- 1) IE Bulletin 79-01B submittal Enclosure #1. 1) Required to operate 100 days for after DBA, not required to 3, 2) NUREG 0737 operated under normal operation.
- 3) ASCO test report AQS 21678KR Rev. A 2) IE Bulletin 79-01B submittal, u, 3) Wear Agine - 40,000 operations at maximum operating pressure 73 differential and nominal voltage.
to 4) See Enclosure 13, item 16.
f03 Present Qualification IEEE 323-1974 4574/b-10/s
Fccility: Fart Calh:un 1 Docket Ns.: 50-285
- C-300 SYSTEM COMPONENT EVALUATION WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAN6-
, CATION ING EQUIPMENT DESCRIPTION specifi- Qualif- Specifi _ Qualifi ,, METHOD ITEMS Parameter :ation cation cation cation -
System: Ele-trical Equipment Operating -
Time :ontinuous Continuous 1 2 Type Test NONE Item No.: N/A Tempera- s, ture *F 305*F 385*F 1 .2 Type Test NONE Component: Splices Pressure PSIg 50 PSIg '6'6 PSIg 1 2 -
s Type Te n NONE Manufacturer: Raychem _.
Relative Model No.: Raychem Breakout Humidity % 100% 100% 1 2 Type, Test- i NONE kits Function: Splices for Inter- Chemical 1700 ppm 6200 ppa g-
? facing in all Systems Spray Boron Boron 1 2 Type Test t
NOhT
- Accuracy - Spec: N/A Worst Case Demon: N/A Radiation 2x107Rads 2.9x10 8 1 2 Type Test NONE Service: All Systems Location: Containment Aging 40 yrs 40 yrs 1 2 Type Test NONE ,
Flood Level Elev: 1000.9' Submer-Above Flood Level: gence , N/A N/A N/A N/A N/A NONE' Documentation
References:
Nctes:
- 1) Enclosure #1.
- 2) Environmental Qualification Test Report of Raychem WCSF-N Nuclear In-Line Cable Splice Assemblies for Raychem Corporation 5/15/80 .
Present Qualification %
IEEE 323-1974 4574/d-1/s
_ _ ~ - . . .. __ . . - - . _ _ _ _ _ _ ~ . _ _ _ . _ . _ _ . - . . _ . . _ _ . _ . _ _ _ _ _
- . _. 4 _ _ _ .__ . .. __ . ,_
4 1
~
Fccility: Fort Colh un 1 -
Docket No.: 50-285 *
. S-301 SYSTEM COMPONENT EVALUATION WORK SHEET
-ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAND-CATION ING EQUIPMENT DESCRIPTION specifi- Qualif- Specifi- Qualifi- METHOD ITDRS Parameter cation cation cation cation System: Electrical Equipment Operating Time Continuous Continuous 2 1 Type Test NONE ;
Iten No.: N/A Tempera- Rs 21 & 22 ture *F 109'F 385'F 2 1 Type Test NONE Component: Splices Pressure PSIg N/A 66 PSIg N/A 1 Type Test NONE Manufacturer: Raychem Relative Rm 21 & 22 ;
Humidity % Type Test Model No.: Raychem Breakout 100% 100% 2 1 NONE kits. .
Function: Splices for Inter- Chemical i facing in all Systems Spray N/A N/A N/A 1 Type Test NONE O
t Accuracy - Spec: N/A Demon: N/A Radiatian Note 1 2.9x10s 3 1 Type Test NONE Service: All Systems Location: Balance of' Aux' Bldg Aging N/A N/A N/A N/A N/A N/A ,
Flood Level Elev: N/A Submer-j Above Flood Level: gence N/A N/A N/A N/A N/A N/A i Documentation
References:
Notes:
I 1) Environmental Qualification Test Report 1) Rm-69 -
2.5x10 5R .
- j. of Raychem WCSF-N Nuclear In-Line Cable Ras 21 & 22 - 7x10sR
! Splice Assemblies for Raychem Corporation 5/15/80 Rm 13 -
4x10sR ,
6x105R
- 2) Combustion Engineering Study " Evaluation of Fort Calhoun Rm 60 -
Safety Injection Pump Room Temperature following a loss Ra 59 - 8x10 8 R i of coolant accident" See OPPD letter to the NRC dated 9/6/79.
- 3) " Implementation Methods and Schedules for NUREG-0578" Section 2.1.6b, Pages 16-19 Figures 4.2-1, 4.2, 4.2.3 & 4.2.4 (December 1979) i Present Qualification IEEE 323-1974
Fccility: Fort Colh un 1 Docket No.: 50-285 S-302 SYSTEM COMPONENT EVALUATION WORK SHEET
$ ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAN6-CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation Syster: Electrical Equipment Operating Time Continuous Continuous 1 2 Type Test NONE Item No.: N/A Tempera-ture 'F 216*F 385'F 1 2 Type Test NONE Component: Splices Pressure PSIg 1.2 PSIg 66 PSIg 1 2 Type Test NONE Manufacturer: Raychem Relative Model No.: Raychem Breakout Humidity % 100% 100% 1 2 Type Test NONE kits Function: Splices for Inter- Chemical 3
facing in all Systems Spray N/A N/A N/A N/A N/A NONE hh Accuracy - Spec: N/A Demon: N/A Radiation .N/A N/A N/A N/A N/A NONE Service: All Systems Location: Room 81 Aging N/A N/A N/A N/A N/A NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) Reference Enclosure #2.
- 2) Environmental Qualification Test Report of Raychem WCSF-N Nuclear In-Line Cable Splice Assemblies for Raychem Corporation 5/15/80 Present Qualification IEEE 323-1974 4574/d-2/s
Fccility: Fcrt Colhoun 1 Dock;t No.: 50-285 S-303 SYSTEM COMPONENT EVALUATION WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OITfSTAND-CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Electrical Equipment Operating Time Continuous Continuous 1 3 Type Test NONE Item No.: N/A Tempera- Rm 21 & 22 ture *F 109'F 346*F 1 3 Type Test NONE Component: Cable Pressure PSIg N/A N/A N/A N/A N/A NONE Manufacturer: Rockbestos Relative Rm 21 & 22 Model No.: Fire Wall III Humidity % 100% 100% 1 3 Type Test NONE Function: Interconnecting - Chemical cables for all Systems Spray N/A N/A N/A N/A N/A NONE
[{
us -
Accuracy - Spec: N/A Demon: N/A Radiation Note 1 2x108 2 3 Type Test NONE Service: All Systems Location: Balance of Aux Bldg Aging N/A N/A N/A N/A N/A NONE .
Flood Level Elev: N/A Submer-Above Flood Level: gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) Combustion Engineering Study " Evaluation of Fort Calhoun 1) Rm 69 - 2.5x10 5R Safety Injection Pump Room Temperature following a Loss Rms 21 & 22 - 7x106 R of Coolant Accident" See OPPD letter to the NRC dated Rm 13 - 4x108 R 9/6/79. Rm 60 - 6x10 5 R
- 2) " Implementation Methods and Schedules for NUREG-0578" Section Rm 59 - 8x10 5 R 2.1.6b, Pages 16-19 Figures 4.2-1, 4.2-2, 4.2-3 & 4.2-4 (December 1979) *
- 3) Qualification of Fire Wall III, Class 1E Electric Cables 2/1/77 Present Qualification IEEE 323-1974
Fccility: Fort Calh:un 1 Dock:t Ns.: 50-285
- C-250 SYSTEM COMPONENT EVALUATION WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OLTISTAND-CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Electrical Equipment Operating Time Continuous Continuous 1 2 Type Test NONE Item No.: N/A Tempera-ture *F 305*F 346*F 1 2 Type Test NONE Component: Cables Pressure PSIg 60 PSIg 113 PSIg 1 2 Type Test NONE Manufacturer: Rockbestos Relative Model No.: Fire Wall III Humidity % 100% 100% 1 2 Type Test NONE Function: Interconnecting Chemical 1700 ppm 3000 ppm
? Cables for all Systems Spray Boron Boron 1 2 Type Test NONE Accuracy - Spec: N/A worst case Demon: N/A Radiation 2x10 7Rads 2x10s 1 2 Type Test NONE Service: All Systems Location: Room 81 Aging 40 yrs 40 yrs 1 2 Type Test NONE ,
Flood Level Elev: 1000.9' Submer-Above Flood Level: gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) Enclosure #1.
- 2) Qualification of Fire Wall III Class IE Electric Cable 2/1/77 Present Qualification IEEE 323-1974 4574/d-4/s
Fccility: Fcrt Calh;un 1 Dot:ket No.: 50-285 S-304 -
SYSTEM COMPONENT EVALUATION 10RK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OtrfSTAND-CATION ING EQUIPMENT DESCRIPTION specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter ration cation cation cation System: Electrical Equipment Operating Time :entinuous Continuous 1 2 Type Test N0hT Item No.: N/A '
Tempera-ture *F 216*F 346*F 1 2 Type Test NONE Component: Cables Pressure PSIg 1.2 PSIg 113 PSIg 1 2 Type Test NONE Manufacturer: Rockbestos Relative Model No.: Fire Wall III Humidity % 100% 100% 1 2 Tyne Test NONE Function: Interconnecting unemical
? Cables for all Systems Spray N/A N/A N/A N/A N/A NONE 5
o Accuracy - Spec: N/A Demon: N/A Radiation N/A N/A N/A N/A N/A NONE Service:.All Systems
' Location: Room 81 Aging N/A N/A N/A N/A N/A NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes: I
- 1) Enclosure #2.
- 2) Qualification of Fire Wall III Class IE Electric Cable 2/1/77 Present Qualification IEEE 323-1974 4574/d-6/s
Fccility: Fort Colh un 1 <
s Dock t N2.: 50-285 C-200 -
SYSTEM COMPONENT EVALUATON WRK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTANDJ g
CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation , ,
System: Radiation Monitoring Operating Time Note 1 Note 2 2 3 Type Test NONE Item No.: RM-091A RM-091B Tempera-ture *F 305*F 357*F 1 3 Type Test NONE Component: Detector Pressure PSIg 60 PSIg Note 2 1 3 Type Test NONE Manufacturer: Victoreen Relative Model No.: 878 Humidity % 100% 100% 1 3 Type Test NONE Function: High range containment Chemical Radiation Area Monitor Spray 1700 ppm 3000 ppm 1 3 Type Test NONE
- T' Note 3 2" Accuracy - Spec: 3 j! Demon: Radiation 1x108R 1x107R 1 3 Type Test NONE 1 Service:
Location: Containment Aging N/A 40 yrs N/A 3 Type Test NONE Flood Level Elev: 1001.0' Submer-Above Flood Level: Yes gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) IE Bulletin 79-01B submittal Enclosure #1. 1) During and continuously after DBA.
7, 2) NUREG 0737 2) 1 year under accident environment.
- 3) Qualification Type Test Data Report for 3) See Enclosure 13 item 16.
u, Class 1E Victoreen High Range Containment
?3 Radiation Area Monitor System T
R3 Present Qualification IEEE 323 1974 4574/b-9/s
Fccility: Fert Calh:un 1 ' .!
Dock 2t No.: 50-285 S-6 . I SYSTEM COMPONENT EVALUATON WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OtTTSTAND-< ;-
CATION ING , j; EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS ;
Parameter cation cation cation cation System: Steam Generator, Operating Feedwater & Blowdown Time Note 1 1000 hrs Note 1 2 Type Test NONE Item No.: HCV-1107B & 1108B t Tempera- I ture *F 216*F 346*F 1 2 Type Test NONE l1 Component: Solenoid Valve #1 Pressure .I PSIg 1.2 PSIg 110 PSIg 1 2 Type Test NONE l Manufacturer: ASCO
. Relative ;
Model No.: NP 8320A175E Humidity % 100% 100% 1 2 Type Test NONE Function: Valve Actuators for Chemical St/ Gen RC-2A & RC-2B Aux FW Spray N/A
. N/A N/A N/A NONE y' inlet valves
-l Accuracy - Spec: N/A u) Demon: N/A Radiation N/A N/A N/A N/A N/A NONE Service: Isolation of Aux FW Lines !
Location: Room 81 Aging N/A 10 yrs N/A 2 Type Test NONE
- Flood Level Elev: 1037.4' Submer- .
Above Flood Level: Yes gence N/A N/A N/A N/A N/A NONE-Documentation
References:
Notes:
- 1) See Enclosure #2. 1) Valves are locked open and do not operate during an
. 2) ASCO Test Report Model AQS 21678/TR event.
12 Present Qualification 5; 'IEEE 323-1974 l~
4574/b-6/s l
Facility: Fort-Calh:un 1 Docket No.: 50-285 S-7 -
SYSTEM COMPONENT EVALUATON WORK SHEET 4
ENVIRONMENT DOCUMENTATON REF. QUALIFI- OITfSTAND-CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Steam Generator, Operating ' l.
Feedwater & Blowdown Time Note 1 1000 hrs Note 1 2 Type Test NONE Item No.: HCV-1107B & 1108B ;!
Tempera- qi i ture *F 216*F 346*F 1 2 Type Test NONE ,,
Component: Solenoid Valve #2 Pressure PSIg 1.2 PSIg 110 PSIg 1 2 Type Test NONE-
, Manufacturer: ASCO 'f l- Relative .
Model No.: NP 8314C29E Humidity % 100% 100% 1 2 Type Test NONE '
Function: Valve Actuators for Chemical i St/ Gen RC-2A & RC-2B Aux IV Spray N/A N/A N/A N/A N/A NONE :
7' inlet valves 'l j Accuracy - Spec: N/A ;
j ' c) Demon: N/A ' Radiation N/A N/A N/A N/A N/A NONE !
i Service: Isolation of Aux FW
- Lines
. Location: Room 81 Aging N/A 10 yrs N/A 2 Type Test NONE l
Flood Level Elev: 1037.4' Submer- ,
Above Flood Level: Yes gence N/A N/A N/A N/A N/A NONE- i
.I i
, Documentation
References:
Notes:
- 1) See Enclosure #2. .
- 1) Valves are locked open and do not operate during an l 7a
'2) ASCO Test Report Model AQS 21678/TR event.
.ro l I
. no Present Qualification 23 IEEE 323-1974 <
lE2 oo BJ 4574/b-5/s l
1
. - , . - - . . _ , . - . , , . - , . , - - - ~. - - - ~ ~ - - - - - - , .- - - - - - - . - - , - , - , - - . - , - . . , ----r.-. - - - , . - --
Fccility: Fort Celhoun 1 Dockct No.: 50-285 S-201 -
SYSTEM COMPONENT EVALUATON M)RK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAhP CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Steam Generator, Operating Feedwater & Blowdown Time Intermitter t 1000 hrs. 1 2 Type Test NONE Item No.: FCV-1368, 1369 -
Tempera-ture *F 216*F 346*F 1 2 Type Test NONE Component: Solenoid Pressure PSIg 1.2 PSIg 110 PSIg 1 2 Type Test N0hT Manufacturer: ASCO ._
Relative Model No.: NPC314C29E Ilumidity % 100% 100% 1 2 Type Test NONE Function: Valve Actuators for Chemical Aux. Feedwater Valves Spray N/A N/A N/A N/A N/A NONE 9' .
C Accuracy - Spec: N/A Demon: N/A Radiation N/A L'/A N/A N/A N/A NONE
'@ Service: Isolation of Aux.
Feedwater Line
- Location
- Room 81 Aging N/A 10 yrs. N/A 2 Type Test NONE Floodk.evelElev: 1037.4' Submer-Above Flood Level: Yes gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) Enclosue: #2.
- 2) ASCO Test Report Model AQS 21678/TR R Present Qualification
@ IEEE 323-1974 3
m 4574/b-7/s O
. _ . .. , .. . . - - . . _ - . - . ... _ _ . - - . . . ~ _ . _ . . - . - _ _ . .- .
Fecility: ; Fort Calhzun'1 Dock:t Ns.: 50-285 i
'S-200 .
SYSTEM COMPONENT EVALUATON WRK SHEET
- ENVIRONMENT DOCUMENTATON REF. QUALIFI- OITTSTANDd CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System:. Steam Generator, Operating Feedwater & Blowdown Time Intermitte st 1000 hrs. 1 2 Type. Test NO"E
- . . Item No.
- FCV-1368, 1369 Tempera-ture 'F 216'F 346*F 1 2 Type Test NONE Component: Soleno'id Pressure PSIg 1.2 PSIg 110 PSIg 1 2 Type Test NONE Manufacturer: ASCO 4 Relative l
'Model No.: NP8314C29E Humidity % 100% 100% 1 2 Type Test NONE t Function: Valve Actuators for Chemical '
Aux. Feedwater Valves Spray N/A N/A N/A N/A N/A NONE
. os g; Accuracy - Spec: N/A Sj Demon: N/A Radiation N/A N/A N/A N/A N/A NONE
. Service: Isolation & Control of Aux. Feedwater Lines !
Location: Room 81 Aging N/A 10 yrs. N/A. 2 Type Test NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: Yes ge'nce N/A N/A N/A N/A N/A NONE !
i Documentation
References:
Notes:
- 1) Enclosure #2. ;
- 2) ASCO Test Report Model AQS 21678/TR ,
i
, t Present Qualification ~
co IEEE 323-1974
- 3 . -
R C3 4574/b-4/s
______m_ _ _ _ . _ _ . - __ ._:,.--_-_., . _ , , . . - . _ . _ . . , . _ _ . _ _ _ . . _ , ,,, ,.
Fccility: Fert Calh:un 1 Dockat No.: 50-285 S-202 -
SYSTEM COMPONENT EVALUATON WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OLTISTAND-CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- Fr! HOD ITEMS Parameter cation cation cation cation System: Steam Generator, Operating Feedwater & Blowdown Time Intermitte at 1000 hrs. 1 2 Type Test NONE Item No.: YCV-1045 Tempera-ture *F 216*F 346*F 1 2 Type Test NONE Component: Solenoid Pressure PSIg 1.2 PSIg 110 PSIg 1 2 Type Test NONE Manufacturer: ASCO Relative Model No.: NP8314C29E Humidity % 100% 100% 1 2 Type Test NONE Function: Valve Actuators for Chemical Aux. Feedwater Valves Spray N/A N/A N/A N/A N/A NONE T
g; Accuracy - Spec: N/A Cj Demon: N/A Radiation N/A N/A N/A N/A N/A NONE Service: Isolation & Control of Aux. Feedwater Line Location: Room 81 Aging N/A 10 yrs. N/A 2 Type Test NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: Yes ge'nce N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) Enclosure #2.
- 2) ASCO Test Report Model AQS 21678/TR Present Qualification IEEE 323-1974 4574/b-2/s
Fccility: Fort Calhoun 1 j
Docket No.: 50-285 S-203 . ;
SYSTEM COMPONENT EVALUATON WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIF1- OUTSTAND- l CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Steam Generator, Operating Feedwater & Blowdown Time Intermitte:it 1000 hrs. 1 2 Type Test NONE Item No.: YCV-1045A, 1045B Tempera-ture *F 216*F 346*F 1 2 Type Test NONE Component: Sclenoid Pressure PSIg 1.2 PSIg 110 PSIg 1 2 Type Test NONE Manufacturer: ASCO Relative Model No.: NP8320A185V Humidity % 100% 100% 1 2 Type Test NONE Function: Valve Actuators for Chemical Spray N/A N/A N/A N/A NONE Aux. Feedwater Valves N/A T
-l Accuracy - Spec: N/A Radiation N/A N/A N/A N/A N/A NONE E3 Demon: N/A Service: Isolation & Control of Aux. Feedwater Line Location: Room 81 Aging N/A 10 yrs. N/A 2 Type Test NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: Yes gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes: {
- 1) Enclosure #2.
- 2) ASCO Test Report Model AQS 21678/TR
, Present Qualification IEEE 323-1974 .
4574/b-3/s .
9
Fccility: Fort Calhsun 1 Dockat No.: 50-285 S-204 -
SYSTEM COMPONENT EVALUATON WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTANDJ
, CATION ING EQUIPMENT Dr.SCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Steam Generator, Operating Feedwater & Blowdown Time Continuous Continuou s 1 2 Type Test NONE Item No.: YCV-1045, YCV-1045A, YCV-1045B, FCV-1368, FCV-1369 Tempera-
, HCV-1107B, 1108B Solenoids #1&2 ture F 216*F 340 F 1 2 Type Test NONE Component: Limit Switch Pressure PSIg 1.2 PSIg 70 PSIg 1 2 Type Test NONE Manufacturer: NAMCO Relative Model No.: EA 180-11302 Humidity % 100% 100% 1 2 Type Test NONE Function: Valve Position Chemical PH 10-11 Indicators Spray N/A Boron 1 2 Type Test NONE i
G Accuracy - Spec: N/A S Demon: N/A Radiation N/A 2x4x108R 1 2 Type Test NONE Service:
Location: Room 81 Aging N/A Note 2 Note 2 Note 2 Type Test NONE Flood Level Elev: 1037.4' Submer-
~
Type Test Above Flood Level: Yes gence Note 1 Note 1 N/A N/A Note 1 NONE Documentation
References:
Nctes:
- 1) Enclosure #2. 1) The switches were sealed and tested to 70 PSIg. The District
- o 2) NAMCO Test Report Model EA180 9/5/78 considers them capable of withstanding submergence.
- 2) Switches qualified for 40 years using NAMCO recommended a Present Qualification maintenance. NAMCO letter dated 7/16/80.
M IEEE 323-1974 -
R H
4574/b-1/s 9
m s
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ -__ . _ _ . . _ . . . . - -. . - ... - _ _ _ _ = _ . . . -. .
9 Fecility: Fort Calhoun 1 Docket No.: 50-285 S-200 .
SYSTEM COMPONENT EVALUATON WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAND-CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation
. :sys tem: Containment Hydrogen Operating 100 days Pc st Purge System Time Note 1 Accident 1 3 Type Test NONE-Item No.: VA-81A & VA-81B Tempera-ture *F N/A N/A N/A N/A N/A NONE Component: Hydrogen Analyzers Pressure PSIg N/A N/A N/A N/A N/A NONE Manufacturer: COMSIP Relative Model No.: Delphi IV Hydrogen Humidity % N/A N/A N/A N/A N/4 NONE Analyzer Function: Containment Atmosphere Chemical Hydrogen Analyzers Spray N/A N/A N/A N/A N/A NONE i
g Accuracy - Spec: Note 2 Note 3
'1 Demon: Radiation 8x10 5R 1x106R 2 3 Type Test NONE ,
Service: Determine % H2 con-concentration in containment Location: Room 59 Aging N/A 5-10 yrs N/A 3 Type Test NONE 11000 Level Elev: N/A Submer- Type Test Above Flood Level: Yes No gence N/A N/A N/A N/A N/A NONE vocementation Meterences: Notes:
- 1) NUREG 0737. 1) Required to operate during and 100 days after DBA
, 2) " Implementation Methods and Schedules for 2) IE Bulletin 79-01B submittal Enclosure #12 NUREG 0578" Section 2.1.6B page 18, fihure 3) See Enclosure 13, Item 16 m 4.2-3 (December 1979)
% 3) COMSIP, Inc. " Test Report IEEE-323-1974
,R Qualification of Delphi IV Hydtogen Analyzer Present Qualification IEEE 323-1974 4574/b4/s
_-.m. __ . . . _ . _ _ . _ _ . - . . _ . _ __ . . - . . _ .
Facility: Fort Calhoun l' ,
~Dockat No.: 50-285 '
C-26J .
I SYSTEM COMPONENT EVALUATON WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAND, ;
CATION ING EQUIPMENT DESCRIPTION Sperifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation <
system: containment Hydrogen Operating Analyzer System Time Note 1 Note 3 2 3 Type Test NONE Item No.: HCV-883C,'883D, 883E, 883F, 883G, 883H, HCV-820C, 820D Tempera-
--820E, 820F, 820G, 820H ture *F 305*F 346*F 1 3 Type Test NONE Component: Electric Solenoid vv Pressure i
~
PSIg 60 PSIg 110 PSIg 1 3 Type Test NONE Manufacturer: ASCO Relative Model No.: X206-381-6RF Humidity % 100% 100% 1 3 Type Test NONE t
Function:-H 2 Analyzer con- Chemical 1700 ppm 3000 ppm tainment sample valve Spray Boron Boron PH : 0 1 3 Type Test NONE
'T' Accuracy - Spec: 'N/A Note 4
' hj j f3 Demon: N/A Radiation 1.6x.10 7R 2x10sR N/A 3 Type Test NONE Service:
Aging Type Test Location: Containment N/A 10 yrs N/A 3 NONE Flooa Level Elev: 1001.0' Submer-Above Flood Level: Yes gence N/A N/A N/A N/A. N/A NONE Locumentation Meterences: Notes:
- 1) IE Bulletin 79-01B submittal Enclosure #1. 1) Required to operate 100 days for after DBA, not required to
- , 2) NUREG 0737 operated under normal operation. i
- 3) ASCO test report.AQS 21678KR Rev. A 2) IE Bulletin 79-01B submittal.
u, 3) Wear Agine - 40,000 operations at maximum operating pressure 73 differential and nominal voltage. ,
- 4) See Enclosure 13, item 16.
lto R3 - Present Qualification IEEE.323-1974 4574/b-10/s
.y.-, .,. - - . . - , _ - - _ _
Fccility: Fort Calhoun 1 Dock t No.: 50-285 C-300 SYSTEM COMPONENT EVALUATION WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAND-CATION ING EQUIPMENT DESCRIPTION 3pecifi- Qualif- Specifi- Qualifi- METHOD ITEMS Pa rameter :ation cation cation cation System: Electrical Equipment Operating Time :ontinuous Continuous 1 2 Type Test NONE Item No.: N/A Tempera-ture *F 305*F 385*F 1 2 Type Test NONE Component: Splices Pressure PSIg $0 PSIg 66 PSIg 1 2 Type Test NONE Manufacturer: Raychem Relative Model No.: Raychem Breakout Humidity % 100% 100% 1 2 Type Test NONE kits Function: Splices for Inter- Chemical 1700 ppm 6200 ppm
? facing in all Systems Spray Boron Boron 1 2 Type Test N0hI 8
7 Accuracy - Spec: N/A Worst Case Demon: N/A Radiation 2x10 7Rads 2.9x10 8 1 2 Type Test NONE Service: All Systems Location: Containment Aging 40 yrs 40 yrs 1 2 Type Test NONE Flood Level Elev: 1000.9' Submer-Above Flood Level: gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) Enclosure #1.
- 2) Environmental Qualification Test Report of Raychem WCSF-N Nuclear In-Line Cable Splice Assemblies for Raychem Corporation 5/15/80 Present Qualification IEEE 323-1974 4574/d-1/s a
Facility: Fort Calhoun 1 Docket No.: 50-285 S-301 SYSTEM COMPONENT EVALUATION WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUISTANi)-
CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD IIT16 Pa rameter cation cation cation cation
~ System: Electrical Equipment Operating Time Continuous Continuous 2 1 Type Test NONE Item No.: N/A Tempera- Rm 21 & 22 ture *F 109*F 385*F 2 1 Type Test NONE Component: Splices Pressure ;
PSIg N/A 66 PSIg N/A 1 Type Test NONE '
Manufacturer: Raychem Relative Rm 21 & 22
-Model No.: Raychem Breakout Humidity % 100% 100% 2 1 Type Test NONE kits Function: Splices for Inter- Chemical !
7' facing in all Systems Spray N/A N/A N/A 1 Type Test NONE 03 Accuracy - Spec: N/A 1 Demon: N/A Radiation Note 1 2.9x10 8 3 1 Type Test NONE Se rvice: All Systems Location: Balance of Aux Bldg Aging N/A N/A N/A N/A N/A N/A ,
! Flood Level Elev: N/A Submer-Above Flood Level: gence N/A N/A N/A N/A N/A N/A Documentation'
References:
Notes:
- 1) Environmental Qualification Test Report 1) Rm 69 -
2.5x10 5R of Raychem WCSF-N Nuclear In-Line Cable Ras 21 & 22 - 7x10 6R Splice- Assemblies for Raychem Corporation 5/15/80 Rm 13 - 4x10 8 R
- 2) Combustion Engineering Study " Evaluation of Fort Calhoun Rm 60 - 6x10 5 R Safety Injection Pump Room Temperature following a loss Rm 59 - 8x10 5 R of coolant accident" See OPPD letter to the NRC dated 9/6/79.
- 3) "Inapienentation Methods and Schedules for NUREG-0578" Section 2.1.6b, Pages 16-19 Figures 4.2-1, 4.2, 4.2.3 & 4.2.4-(December 1979)
Present Qualification IEFJ. 323-1974
I Fccility: Fort Calhoun 1 Dock t No.: 50-285 S-302 -
SYSTEM COMPONENT EVALUATION WORK SHEET ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAND-CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Electrical Equipment Operating j Time Continuous Continuous 1 2 Type Test NONE Item No.: N/A Tempera-ture 'F 216*F 385 F 1 2 Type Test NONE Component: Splices Pressure PSIg 1.2 PSIg 66 PSIg 1 2 Type Test NONE Manufacturer: Raychem Relative Model No.: Raychem Breakout Humidity % 100% 100% 1 2 Type Test NONE l kits Function: Splices for Inter- Chemical y, facing in all Systems Spray N/A N/A N/A N/A N/A NONE
. a, '
lg Accuracy - Spec: N/A Demon: N/A Radiation N/A N/A N/A N/A N/A NONE Service:- All Systems Location: Room 81 Aging N/A N/A N/A N/A N/A NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) Reference Enclosure #2.
- 2) Environmental Qualification Test Report of Raychem WCSF-N Nuclear In-Line Cable Splice Assemblies for Raychem Corporation 5/15/80 Present Qualification IEEE 323-1974 4574/d-2/s
Fccility: Fort Calhoun 1 Dock t No.: 50-285 S-303 SYSTEM COMPONEhT EVALUATION WORK SHEET -
ENVIRONMEhT DOCUMENTATON REF. QUALIFI- OUTSTAND-CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Electrical Equipment Operating Time Continuous Continuous 1 3 Type Test NONE Item No.: N/A Tempe ra- Rm 21 & 22 ture *F 109 F 346 F 1 3 Type Test NONE Component: Cable Pressure PSIg N/A N/A N/A N/A N/A NONE Manufacturer: Rockbestos Relative Rm 21 & 22 Model No.: Fire Wall III Humidity % 100% 100% 1 3 Type Test NONE Function: Interconnecting - Chemical T' cables for all Systems Spray N/A N/A N/A N/A N/A NONE 05 -
Accuracy - Spec: N/A Demon: N/A Radiation Note 1 2x108 2 3 Type Test NONE Service: All Systems Location: Balance of Aux Bldg Aging N/A N/A N/A N/A N/A NONE Flood Level Elev: N/A Submer-Above Flood Level: gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) Combustion Engineering Study " Evaluation of Fort Calhoun 1) Rm 69 - 2.5x10 5 R Safety Injection Pump Room Temperature following a Loss Rms 21 & 22 - 7x10 8 R of Coolant Accident" See OPPD letter to the NRC dated Rm 13 - 4x10 8 R 9/6/79. Rm 60 - 6x10sR
- 2) " Implementation Methods and Schedules for NUREG-0578" Section Rm 59 - 8x10 5 R 2.1,6b, Pages 16-19 Figures 4.2-1, 4.2-2, 4.2-3 & 4.2-4 (December 1979)
- 3) Qualification of Fire Wall III, Class IE Electric Cables 2/1/77 Present Qualification IEEE 323-1974
Fccility: Fort Calhoua 1 Dock 2t No.: 50-285 C-250 SYSTEM COMPONENT EVALUATION VORK SHEET -
ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAND-CATION ING EQUIPMENT DESCRIPTION Ppecifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter kation cation cation cation System: Electrical Equipment Operating Time Continuous Continuous 1 2 Type Test NONE Item No.: N/A Tempera-ture *F 305 F 346*F 1 2 Type Test NONE Component: Cables Pressure PSIg 60 PSIg 113 PSIg 1 2 Type Test NONE Manufacturer: Rockbestos Relative Model No.: Fire Wall III Humidity % 100% 100% 1 2 Type Test NONE Function: Interconnecting Chemical 1700 ppm 3000 ppm O'
Cables for all Systems Spray Boren Boron 1 2 Type Test NONE E' -
' Accuracy - Spec: N/A Worst Case Demon: N/A Radiation 2x10 7Rads 2x108 1 2 Type Test NONE Se rvice: All Systems Location: Room 81 Aging 40 yrs 40 yrs 1 2 Type Test NONE Flood Level Elev: 1000.9' Submer-Above Flood Level: gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) Enclosure #1.
- 2) Qualification of Fire Wall III Class IE Electric Cable 2/1/77 Present Qualification IEEE 323-1974 4574/d-4/s
Fccility: Fort Calbrun 1 Docket No.: 50-285 S-304 -
SYSTEM COMPONENT EVALUATION M)RK SHEET -
ENVIRONMENT DOCUMENTATON REF. QUALIF7.- OUTSTANI)-
CATION It'~
EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter ration cation cation cation System: Electrical Equipment Operating Time :ontinuous Coctinuous 1 2 Type Test N0hI Item No.: N/A '
Tempera- >
ture F 216*F 346*F 1 2 Type Test NONE Component: Cables Pressure PSIg 1.2 PSIg 113 PSIg 1 2 Type Test NONE Manufacturer: Rockbestos Relative Model No.: Fire Wall III Humidity % 100% 100% 1 2 Type Test NONE Function: Interconnecting unemical y Cables for all Systems Spray N/A N/A N/A N/A N/A N0hT
- g. .
c7 Accuracy - Spec: N/A Demon: N/A Radiation N/A N/A N/A N/A N/A NONE Service:.All Systems.
Location: Room 81 Aging N/A N/A N/A N/A N/A N0hT Flood Level Elev: 1037.4' Submer-Above Flood Level: gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) Enclosure #2.
- 2) Qualification of Fire Wall III Class IE Electric Cable 2/1/77 Present Qualification IEEE 323-1974 4574/d-6/s F
4
Fccility: Fort Calhoun 1 Docket No.: 50-285 C-200 -
SYSTEM COMPONFET EVALUATON KORK SHEET .
ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAND-CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- MFTHOD ITEMS Parameter cation cation cation cation System: Radiation Monitoring Operating Time Note 1 Note 2 2 3 Type Test NONE Item No.: RM-091A RM-091B Tempera-ture *F 305 F 357 F 1 3 Type Test NONE Component: Detector Pressure PSIg 60 PSIg Note 2 1 3 Type Test NONE Manufacturer: Victoreen Relative Model No.: 878 Humidity % 100% 100% 1 3 Type Test NONE Function: High range containment Chemical Radiation Area Monitor Spray 1700 ppm 3000 ppm 1 3 Type Test NONE i
E; Accuracy - Spec: Note 3 j3 Demon: Radiation 1x106R 1x107R 1 3 Type Test NONE Service:
Location: Containment Aging N/A 40 yrs N/A 3 Type Test NONE Flood Level Elev: 1001.0' Submer-Above Flood Level: Yes gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) IE Bulletin 79-01B submittal Enclosure #1. 1) During and continuously after DBA.
7, 2) NUREG 0737 2) 1 year under accident environment.
- 3) Qualification Type Test Data Report for 3) See Enclosure 13 item 16.
u, Class IE Victoreen High Range Containment
?3 Radiation Area Monitor System
. R3 Present Qualification IEEE 323-1974 4574/b-9/s
Fccility: Fort Calhoun 1 Docket No.. 50-285 S-6 .
SYSTEM COMPONENT EVALUATON WORK SHEET ,
ENVIRONMENT DOCUMENTATON REF. QUALIFI- OITISTAND-CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Steam Generator, Operating Feedwater & Blowdown Time Note 1 1000 hrs Note 1 2 Type Test NONE Item Nc.: HCV-1101u & 1108B Tempera-ture F 216 F 346 F 1 2 Type Test NONE Component: Solenoid Valve #1 Pressure PSIg 1.2 PSIg 110 PSIg 1 2 Type Test NONE Manufacturer: ASCO Relative Model No.: NP 8320A175E Humidity % 100% 100% 1 2 Type Test NONE Function: Valve Actuators for Chemical St/ Gen RC-2A & RC-2B Aux FW Spray N/A N/A N/A N/A N/A NONE 7' inlet valves u)
Accuracy - Spec: N/A Demon: N/A Radiation N/A N/t. N/A N/A N/A NONE Service: Isolation of Aux FW Lines Location: Room 81 Aging N/A 10 yrs N/A 2 Type Test NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: Yes gence N/A N/A N/A N/A N/A NONE-Documentation
References:
Notes:
- 1) See Enclosure #2. 1) Valves are locked open and do not operate during an
- 2) ASCO Test Report Model AQS 21678/TR event.
Ed Present Qualification g; IEEE 323-1974 I3 m
4574/b-6/s
Fccility: Fort C:1houn 1 Docket No.: 50-285 S-7 .
SYSTEM COMPONENT EVALUATON WORK SHEET ,
ENVIRONMEhT DOCUMEhTATON REF. QUALIFI- OLTISTAND-CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Pa rame ter cation cation cation cation System: Steam Generator, Operating Feedwater & Blowdown Time Note 1 1000 hrs Note 1 2 Type Test NONE Item No.: HCV-1107B & 1108B Tempera-ture F 216 F 346 F 1 2 Type Test NONE Component: Solenoid Valve #2 Pressure PSIg 1.2 PSIg 110 PSIg 1 2 Type Test NONE Manufacturer: ASCO Relative Model No.: NP 8314C29E Humidity % 100% 100% 1 2 Type Test NONE Function: Valve Actuators for Chemical St/ Gen RC-2A & RC-2B Aux FW Spray N/A N/A N/A N/A N/A NONE T' inlet valves g; j Accuracy - Spec: N/A c) Demon: N/A Radiation N/A N/A N/A N/A N/A NONE Service: Isolation of Aux FW Lines Location: Room 81 Aging N/A 10 yrs N/A 2 Type Test NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: Yes gence N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) See Enclosure #2. 1) Valves are locked open and do not operate during an
- 2) ASCO Test Report Model AQS 21678/TR event.
n3 Present Qualification 22 IEEE 323-1974 2
l R$
4574/b-5/s
Fccility: Fort Calhoun 1 Dockst No.: 50-285 S-201 .
SYSTEM COMPONENT EVALUATON WORK SHEET .
ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAND.
CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Steam Generator,. Operating Feedwater & Blowdown Time Intermitter t 1000 hrs. 1 l2 Type Test NONE Item No.: FCV-1368, 1369 -
Tempera-ture F 216 F 346 F 1 2 Type Test N0hI Component: Solenoid Pressure PSIg 1.2 PSIg 110 PSIg 1 2 Type Test NONE Manufacturer: ASCO . _ _ _
Relative Model No.: NP8314C29E Humidity % 100% 100% 1 2 Type Test NONE Functica: Valve Actuators for Chemical Aux. Feedwater Valves Spray N/A N/A N/A N/A N/A NONE T _.
G Accuracy - Spec: N/A
@ Demon: N/A Radiation N/A N/A N/A N/A N/A NONE Service: Isolation of Aux.
Feedwater Line Location: Room 81 Aging N/A 10 yrs. N/A 2 T3Te Test NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: Yes gence N/A N/A N/A N/A N/A NONE t
Documentation
References:
Notes:
- 1) Enclosure #2.
- 2) ASCO Test Report Model AQS 21678/TR
.R Present Qualification
@ IEEE 323-1974 .
1N 4574/b-7/s
[
1
'Fecility:. Fort Calhoun'1 Docket No.: 50-285 S-200 .
SYSTEM COMPONENT EVALUATON WORK SHEET .
ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTMD<
CATION ING
-EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Pa rameter cation cation cation cation )
System: Steam Generator, Operating Feedwater & Blowdown Time Intermitte it 1000 hrs. I 2 Type Test NONE Item No.: FCV-1368, 1369 Tempera-ture *F 216 F 346*F 1 2 Type Test NONE
\
Component: Solenoid Pressure PSIg 1.2 PSIg 110 PSIg 1 2 Type Test NONE Manufacturer: ASCO Relative Model No.: NP8314C29E Humidity % 100% 100% 1 2 Type Test NONE Function:' Valve Actuators for Chemical Aux..Feedwater Valves Spray N/A N/A N/A N/A N/A NONE os.
g3 Accuracy - Spec: N/A
@j Demon: N/A Radiation N/A N/A N/A N/A N/A NONE Service: Isolation & Control of Aux. Feedwater Lines Location: Room'81 Aging N/A 10 yrs. _
N/A 2 Type Test NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: Yes gence N/A N/A N/A N/A N/A NONE Documentation
References:
, Notes:
- 1) Enclosure #2.
- 2) ASCO Test Report Model AQS 21678/TR Present Qualification fw IEEE 323-1974 A
4
-l$ 4574/b-4/s
~
1
Fecility: Fort Celhoun 1 Docket No.: 50-285 S-202 ,
SYSTEM COMPONENT EVALUATON WORK SHEET .,
ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTANDi CATION ING EQUIPMENT DF.SCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Steam Generator, Operating Feedwater & Blowdown Time Inte rmitte it 1000 hrs. 1 2 Type Test NONE Item No.: YCV-1045 Tempera-ture F 216*F 346 F 1 2 Type Test NONE 4~
Component: Solenoid Pressure PSIg 1.2 PSIg 110 PSIg 1 2 Type Test NONE Manufacturer: ASCO f' Relative Model No.: NP8314C29E Ilumidity % 100% 100% 1 2 Type Test NONE Function: Valve Actuators for Chemical Aux. Feedwater Valves Spray N/A N/A N/A N/A N/A NONE i
,j -
Accuracy - Spec: N/A NCNE cq Demon: N/A Radiation N/A N/A N/A N/A N/A Se rvice : Isolation & Control of Aux. Feedwater Line {
Location: Room 81 Aging N/A 10 yrs. N/A 2 Type Test NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: Yes ge'nce N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
f
- 1) Enclosure #2.
- 2) ASCO Test Report Model AQS 21678/TR i, Present Qualification IEEE 323-1974 4574/b-2/s
Facility: Fort Calhoun 1 Docket No.: 50-285 S-203 .
SYSTEM COMPONENT EVALUATON WRK SHEET .
t ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTAND <
CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Pa rameter cation cation cation ' cation System: Steam Generator, Operating Feedwater & Blowdown Time Intermitteat 1000 hrs. 1 2 Type Test NONE Item No.: YCV-1045A, 1045B Tempera-ture F 216 F 346 F 1 2 Type Test NONE Component: Solenoid Pressure PSIg 1.2 PSIg 110 PSIg 1 2 Type Test NONE Manufacturer: ASCO --
Relative Model No.: NP8320A185V Humidity % 100% 100% 1 1 Type Test NONE Function: Valve Actuators for Chemical Aux. Feedwater Valves Spray N/A N/A N/A N/A N/A NONE i
g; Accuracy - Spec: N/A E3 Demon: N/A Radiation N/A N/A N/A N/A N/A NONE Service: Isolation & Control of Aux. Feedwater Line Location: Room 81 Aging N/A 10 yrs. N/A 2 Type Test NONE Flood Level Elev: 1037.4' Submer-Above Flood Level: Yes ge'ce n N/A N/A N/A N/A N/A NONE Documentation
References:
Notes:
- 1) Enclosure #2.
- 2) ASCO Test Report Model AQS 21678/TR
- Present Qualification IEEE 323-1974 4574/b-3/s o
Fecility: Fort Calhoun 1 Docket No.: 50-285
- S-204 ,
SYSTEM COMPONENT EVALUATON WORK SHEET .
ENVIRONMENT DOCUMENTATON REF. QUALIFI- OUTSTANDa CATION ING EQUIPMENT DESCRIPTION Specifi- Qualif- Specifi- Qualifi- METHOD ITEMS Parameter cation cation cation cation System: Steam Generator, Operating Feedwater & Blowdown Time Continuous Continuou s 1 2 Type Test NONE Item No.: YCV-1045, YCV-1045A, YCV-1045B, FCV-1368, FCV-1369 Tempera-HCV-1107B, 1108B Solenoids #1&2 ture F 216 F 340*F 1 2 Type Test NONE Component: Limit Switch Pressure PSIg 1.2 PSIg 70 PSIg 1 2 Type Test NONE Manufacturer: NAMCO Relative Model No.: EA 180-11302 Humidity % 100% 100% 1 2 Type Test NONE Function: Valve Position Chemical PH 10-11 Indicators Spray N/A Boron 1 2 Type Test NONE e il s' Accuracy - Spec: N/A gj Demon: N/A Radiation N/A 2x4x108R 1 2 Type Test NONE Service:
Location: Room 81 Aging N/A Note 2 Note 2 Note 2 Type Test NONE Flood Level Elev: 1037.4' Submer-
~
Type Test Above Flood Level: Yes gence Note 1 Note 1 N/A N/A Note 1 NONE Documentation
References:
Notes:
- 1) Enclosure #2. 1) The switches were sealed and tested to 70 PSIg. The District 7o 2) NAMCO Test Report Model EA180 9/5/78 considers them capable of withstanding submergence.
- 2) Switches qualified for 40 years using NAMCO recommended cg Present Qualification maintenance. NANCO letter dated 7/16/80.
?3 IEEE 323-1974-A l0 4574/b-1/s 4