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Category:CORRESPONDENCE-LETTERS
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999
Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached
ML20217G9261999-10-15015 October 1999
Forwards Insp Rept 50-285/99-10 on 990913-17.One NCV Noted
ML20217G2331999-10-14014 October 1999
Forwards Insp Rept 50-285/99-09 on 990913-17.No Violations Noted
LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999
Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util
LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999
Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls
ML20217B5111999-10-0606 October 1999
Forwards Amend 193 to License DPR-40 & Safety Evaluation. Amend Revises TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance require- Ments for RCS Flow Rate
ML20216H7231999-09-29029 September 1999
Informs That Util 980325 Response to GL 97-06, Degradation of SG Internals, Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Fort Calhoun Station,Unit 1
ML20212L9571999-09-27027 September 1999
Informs That Follow Up Insp for Drill/Exercise Performance Indicator Will Be Conducted During Wk of 991001
LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999
Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl
LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999
Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl
LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999
Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams
LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999
Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls
LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999
Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection
LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999
Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters
IR 05000285/19990081999-09-0707 September 1999
Forwards Insp Rept 50-285/99-08 on 990907-0811.No Violations Noted.Insp Consisted of Exam of Activities Conducted Under License as Relate to Safety & to Compliance with Commission Rules & Regulations & with Conditions of License
ML20211P2581999-09-0303 September 1999
Forwards Insp Rept 50-285/99-06 on 990809-12.No Violations Noted.Insp Consisted of Exam of Activities Under License as Related to EP & to Compliance with Commission Rules & Regulations & with Conditions of License
LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999
Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase
ML20211J9231999-09-0202 September 1999
Forwards SE Accepting Licensee 990301 Requests for Relief Re Third 10-year ISI Interval for Plant,Unit 1.Relief Proposed Alternatives to Requirements in ASME B&PV Section XI,1989 Edition,Paragraphs IWA-5242(a) & IWA-5250(a)(2)
ML20211L3241999-09-0202 September 1999
Informs That Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) of Amend 192 to License DPR-40 Issued on 990727.Corrected Page Encl
LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999
Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld
ML20211F4491999-08-25025 August 1999
Forwards Ltr from Ja Miller,Dtd 990819,which Notified State of Iowa of Deficiency Identified During 990810,Fort Calhoun Station Biennial Exercise.One Deficiency Identified for Not Adequately Demonstrating Organizational Capability
LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999
Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)
LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999
Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld
ML20210R1491999-08-13013 August 1999
Forwards Insp Rept 50-285/99-07 on 990719-23.No Violations Noted.Nrc Identified One Issue Which Was Evaluated Under Risk Significance Determination Process & Was Determined to Be of Low Risk Significance
LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20211B7881999-08-10010 August 1999
Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714
ML20210N1991999-08-0909 August 1999
Informs That as Result of NRC Review of Licensee Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2
ML20210P8991999-08-0909 August 1999
Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill
LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999
Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999
Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999
Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331
LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999
Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program
ML20210G1851999-07-27027 July 1999
Forwards Amend 192 to License DPR-40 & Safety Evaluation. Amend Consists of Changes to TS in Response to 990129 Application
LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999
Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630
ML20216D6951999-07-26026 July 1999
Informs That During 990614 Review of Fort Calhoun,Nrc Noted That Drill/Exercise Performance Indicator Has Entered White Band,Which Indicated Level of Licensee Performance That Warranted Increased Regulatory Response
LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999
Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates
LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999
Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld
ML20210D9471999-07-22022 July 1999
Forwards Amend 191 to DPR-40 & Safety Evaluation.Amend Authorizes Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation
ML20210C2041999-07-20020 July 1999
Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations
ML20210C0201999-07-20020 July 1999
Informs That Due to Administrative Oversight,Revised TS Bases Provided in to Fort Calhoun Station Were Not Dated.Dated Pages to TS Encl
ML20210B0761999-07-19019 July 1999
Forwards Insp Rept 50-285/99-05 on 990601-0710.No Violations Noted
ML20209G5351999-07-15015 July 1999
Informs That Staff Incorporated Rev of TS Bases Provided by Licensee Ltr Dtd 980904,into Fort Calhoun Station Tss. Staff Finds Revs to Associated TS Bases to Be Acceptable. Revised Bases Pages Encl
ML20209F5741999-07-12012 July 1999
Ack Receipt of Transmitting Exercise Scenario for Upcoming Biennial Offsite Exercise Scheduled 990810.Scenario Reviewed & Acceptable
ML20209G5591999-07-0808 July 1999
Forwards Detailed Listing of Staff Concerns with C-E TR NPSD-683,rev 3 & RCS pressure-temperature Limits Rept
LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999
Forwards Fort Calhoun Performance Indicators Rept for May 1999
LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999
Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld
ML20209D8771999-07-0101 July 1999
Summarizes 990630 Public Meeting Conducted in Fort Calhoun, Ne Re Results of Completed Culture Survey,Plant Status, Facility Activities Re New NRC Oversight Process & License Renewal.Licensee Handout & Attendance List Encl
LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999
Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999
Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached
LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999
Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util
LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999
Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls
LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999
Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl
LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999
Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl
LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999
Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams
LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999
Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls
LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999
Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection
LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999
Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters
LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999
Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase
LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999
Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld
LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999
Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld
LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999
Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)
LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required
LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999
Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable
LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999
Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999
Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331
LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999
Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program
LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999
Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates
LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999
Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630
LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999
Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld
LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999
Forwards Fort Calhoun Performance Indicators Rept for May 1999
LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999
Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld
LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999
Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624
LIC-99-0061, Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl1999-06-30030 June 1999
Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl
LIC-99-0056, Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-061999-06-22022 June 1999
Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-06
LIC-99-0059, Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning1999-06-22022 June 1999
Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning
LIC-99-0054, Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 9908101999-06-0808 June 1999
Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 990810
LIC-99-0052, Forwards Fort Calhoun Station Performance Indicators, for Apr 19991999-06-0202 June 1999
Forwards Fort Calhoun Station Performance Indicators, for Apr 1999
LIC-99-0045, Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl1999-05-26026 May 1999
Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl
LIC-99-0046, Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise1999-05-12012 May 1999
Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise
LIC-99-0028, Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage1999-04-30030 April 1999
Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage
LIC-99-0036, Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F1999-04-28028 April 1999
Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F
LIC-99-0043, Forwards Fort Calhoun Performance Indicators Rept for Mar 19991999-04-28028 April 1999
Forwards Fort Calhoun Performance Indicators Rept for Mar 1999
LIC-99-0041, Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager1999-04-27027 April 1999
Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager
LIC-99-0037, Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue1999-04-26026 April 1999
Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue
LIC-99-0039, Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a1999-04-20020 April 1999
Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a
LIC-99-0038, Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl1999-04-20020 April 1999
Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl
LIC-99-0033, Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps1999-04-15015 April 1999
Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps
LIC-99-0035, Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure1999-04-0808 April 1999
Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure
LIC-99-0031, Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate1999-03-31031 March 1999
Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate
LIC-99-0032, Forwards Fort Calhoun Station Performance Indicators, for Feb 19991999-03-31031 March 1999
Forwards Fort Calhoun Station Performance Indicators, for Feb 1999
LIC-99-0029, Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques1999-03-30030 March 1999
Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques
LIC-99-0027, Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld1999-03-16016 March 1999
Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld
LIC-99-0022, Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl1999-03-12012 March 1999
Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl
LIC-99-0024, Informs That OPPD Withdraws Applications Submitted by 950626 &1999-03-12012 March 1999
Informs That OPPD Withdraws Applications Submitted by 950626 &
LIC-99-0016, Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives1999-03-0101 March 1999
Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives
LIC-99-0023, Forwards FCS Performance Indicators for Jan 19991999-03-0101 March 1999
Forwards FCS Performance Indicators for Jan 1999
LIC-99-0020, Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included1999-02-24024 February 1999
Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included
LIC-99-0011, Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 11999-02-0505 February 1999
Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 1
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARLIC-90-0705, Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl1990-09-17017 September 1990
Forwards Suppl to 900906 Application for Amend to License DPR-40,making Administrative Changes to Tech Specs. Justification & NSHC Analysis for Changes Encl
LIC-90-0745, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions1990-09-17017 September 1990
Responds to NRC Re Violations Noted in Insp Rept 50-285/90-32.Corrective Actions:Enhancements Made to Facility Mod Procedures & Engineering Instructions
LIC-90-0717, Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-071990-09-13013 September 1990
Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07
LIC-90-0716, Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls1990-09-13013 September 1990
Forwards Ref Matl for Preparing Reactor Operator Licensing Exams Scheduled for 901113.W/o Encls
LIC-90-0740, Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits1990-09-12012 September 1990
Forwards Rev 0 to EA-FC-90-062, Diesel Generator Upper Temp Operating Limits,Engineering Analysis. Both Generators Operable & Will Perform Safety Function Consistent W/ Specified Ambient Air Temp Limits
LIC-90-0741, Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets1990-09-0707 September 1990
Submits Plan for Replacement of Remaining Two Control Element Assemblies Which Contain All B4C Pellets
LIC-90-0440, Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes1990-09-0606 September 1990
Forwards Application for Amend to License DPR-40,revising Tech Specs to Make Administrative Changes
LIC-90-0667, Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 9005291990-09-0404 September 1990
Responds to NRC Re Violations Noted in Insp Rept 50-285/90-30 Re Inadequate post-maint Testing Instructions. Corrective Actions:Maint Work Order Written & Performed to Tighten Actuator Diaphragm Bolts on 900529
LIC-90-0712, Forwards fitness-for-duty Program Performance Data for Period of Jan-June 19901990-08-31031 August 1990
Forwards fitness-for-duty Program Performance Data for Period of Jan-June 1990
LIC-90-0683, Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations1990-08-27027 August 1990
Forwards Responses to Recommendations in SALP Rept 50-285/90-24.Util Currently Developing Corporate Level Procedure to Provide Guidance on Operability Determinations
LIC-90-0627, Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection1990-08-22022 August 1990
Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection
LIC-90-0670, Forwards Fort Calhoun Station Performance Indicators for Jul 19901990-08-22022 August 1990
Forwards Fort Calhoun Station Performance Indicators for Jul 1990
LIC-90-0662, Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution1990-08-22022 August 1990
Forwards Rev 1 to Monthly Operating Rept for June 1990 for Fort Calhoun Station Unit 1,for Proper Distribution
LIC-90-0673, Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl1990-08-22022 August 1990
Retransmits Original Response of Util Responding to Violations Noted in Insp Rept 50-285/90-25.W/o Encl
LIC-90-0636, Forwards Results of 1990 Refueling Outage Inservice Insp & Rept for Repairs or Replacement1990-08-13013 August 1990
Forwards Results of 1990 Refueling Outage Inservice Insp & Rept for Repairs or Replacement
LIC-90-0591, Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-21990-08-13013 August 1990
Provides Info Re RCS Leak Detection Sys to Detect Leaks from Primary Piping Sys to Containment,Per Generic Ltr 84-04 & USI A-2
LIC-90-0631, Responds to Generic Ltr 89-15 Re NRC Solicitation of Utils to Voluntarily Participate Emergency Response Data Sys Program.Util Prepared to Work W/Nrc to Investigate Actions Necessary to Implement Program at Plant1990-08-0808 August 1990
Responds to Generic Ltr 89-15 Re NRC Solicitation of Utils to Voluntarily Participate Emergency Response Data Sys Program.Util Prepared to Work W/Nrc to Investigate Actions Necessary to Implement Program at Plant
LIC-90-0485, Confirms Interim Resolution of Identified Problem Associated W/Use of Input Variable for PORV Opening Time in Calculation of Low Temp Overpressure Protection Sys Setpoints1990-08-0707 August 1990
Confirms Interim Resolution of Identified Problem Associated W/Use of Input Variable for PORV Opening Time in Calculation of Low Temp Overpressure Protection Sys Setpoints
LIC-90-0645, Forwards Application for Amend to License DPR-40,making Typo & Administrative Corrections to Tech Specs1990-08-0202 August 1990
Forwards Application for Amend to License DPR-40,making Typo & Administrative Corrections to Tech Specs
LIC-90-0647, Informs That Tl Patterson Assumed Position of Plant Manager, Effective 9008011990-08-0101 August 1990
Informs That Tl Patterson Assumed Position of Plant Manager, Effective 900801
LIC-90-0659, Advises of Plans to Achieve Operability of Third Auxiliary Feedwater Pump by 9008101990-07-31031 July 1990
Advises of Plans to Achieve Operability of Third Auxiliary Feedwater Pump by 900810
LIC-90-0449, Forwards Rev 1 to EA-FC-90-037, Control Room Habitability Evaluation for NUREG-0737,Item III.D.3.41990-07-20020 July 1990
Forwards Rev 1 to EA-FC-90-037, Control Room Habitability Evaluation for NUREG-0737,Item III.D.3.4
LIC-90-0588, Provides Notification of SPDS Implementation at Plant,Per1990-07-19019 July 1990
Provides Notification of SPDS Implementation at Plant,Per
LIC-90-0585, Forwards Simulator Malfunction Cause & Effects1990-07-18018 July 1990
Forwards Simulator Malfunction Cause & Effects
ML20055D9351990-07-0202 July 1990
Forwards Fort Calhoun Station Performance Indicators,May 1990
LIC-90-0564, Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility1990-06-29029 June 1990
Forwards Updated, Position Paper Re Seismic Capability of Welded Steel Piping. Documentation Demonstrates No Generic Thermal or Seismic Safety Issue Exists for Welded Steel Small Diameter Piping at Facility
LIC-90-0522, Forwards Revised Response to Notice of Deviation from Insp Rept 50-285/90-02.Corrective Actions:Cable Trays 5-4A & 5-4B Reworked to Neatly Tie Down Cables & Remove Crossovers & Engineering Instruction GEI-9 on Electrical Sys Updated1990-06-29029 June 1990
Forwards Revised Response to Notice of Deviation from Insp Rept 50-285/90-02.Corrective Actions:Cable Trays 5-4A & 5-4B Reworked to Neatly Tie Down Cables & Remove Crossovers & Engineering Instruction GEI-9 on Electrical Sys Updated
LIC-90-0566, Forwards 1990/1991 Statement of Cash Flow from Operations. Cash Flow Statement Deviates from Reg Guide 9.4 Due to Util Being Political Subdivision of State of Ne1990-06-29029 June 1990
Forwards 1990/1991 Statement of Cash Flow from Operations. Cash Flow Statement Deviates from Reg Guide 9.4 Due to Util Being Political Subdivision of State of Ne
LIC-90-0488, Responds to Request for Info Re Status of Implementation of Generic Safety Issue Requirements1990-06-29029 June 1990
Responds to Request for Info Re Status of Implementation of Generic Safety Issue Requirements
LIC-90-0446, Forwards Application for Amend to License DPR-40,to Restrict Containment Spray Use as Backup for Shutdown Cooling in Tech Specs1990-06-28028 June 1990
Forwards Application for Amend to License DPR-40,to Restrict Containment Spray Use as Backup for Shutdown Cooling in Tech Specs
LIC-90-0429, Forwards Application to Amend License DPR-40,adding Hydrogen Purge Sys to Tech Spec.Discussion,Justification & NSHC Analysis for Amend,Provided1990-06-28028 June 1990
Forwards Application to Amend License DPR-40,adding Hydrogen Purge Sys to Tech Spec.Discussion,Justification & NSHC Analysis for Amend,Provided
ML20043J0611990-06-22022 June 1990
Responds to NRC 900523 Ltr Re Violations Noted in Insp Rept 50-285/90-29.Corrective Actions:Five Chemistry Technicians Provided Refresher Training on 900427 on Existing EPIP-EOF-6
ML20044A1631990-06-22022 June 1990
Requests That NRC Continue Processing Exemption Request for Configuration of wide-range Nuclear Instrumentation Cables in Fire Area 34B (Upper Electrical Penetration Room). Emergency Boration Added to Achieve Safe Shutdown
ML20044A4961990-06-18018 June 1990
Forwards Supplemental Application for Amend to License DPR-40,making Administrative Corrections to Tech Specs. Procedure SO-G-70, Chemical Control Also Encl
ML20043G2981990-06-14014 June 1990
Provides Followup to Special Rept on Inoperable Fire Barriers.Eight Inoperable Dampers Replaced Under Mod MR-FC-87-036, Fire Damper Replacement. Remaining 38 Dampers Found to Be Acceptable After Damper Design Review
ML20043E6451990-06-0808 June 1990
Provides Supplemental Response to Generic Ltr 88-17 & NRC Bulletin 80-12.Plant Pumps & Suction Header Piping Not Originally Constructed for Use as Backup to LPSI Sys for Shutdown Cooling
ML20043E0071990-06-0101 June 1990
Discusses Rev to Previous Commitments Made in Response to Requirements of 10CFR50,App R,Section Iii.G Re post-fire Repairs to Equipment Required for Cold Shutdown Following Fire in Fire Area 6
ML20043G3281990-06-0101 June 1990
Advises That Personnel at Util Reviewed Reactor Operator Licensing Exam Administered on 900529.Comments on Exam Encl
ML20043C1811990-05-29029 May 1990
Advises That Util Has Cleaned RW HXs AC-1A & AC-1D & Will Clean AC-1C by 900615
ML20043B4981990-05-24024 May 1990
Updates Schedule for Submitting Results of PORV Block Valve Prototype Testing.Establishment of Test Parameters & Development of Test Procedures Tentatively Scheduled for Submittal in Nov 1990.Final Rept Expected by 910630
ML20043B5061990-05-23023 May 1990
Advises That Testing to Verify Operability of Hydrogen Purge Sys Successfully Completed During 1990 Refueling Outage.Proposed Tech Spec Rev Will Be Submitted by 900701
ML20043B4731990-05-23023 May 1990
Forwards Fort Calhoun Station Performance Indicators, Monthly Rept for Apr 1990
ML20043A7821990-05-18018 May 1990
Advises That Licensee Plans to Replace Valves HCV-247 & HCV-2988 During 1991 Refueling Outage Pending Successful Redesign & Retesting of New Valves by Valcor
ML20043A8021990-05-18018 May 1990
Advises That Walkdown of safety-related Portions of Plant to Verify Accuracy of Fire Barrier Penetration Drawings & Surveillance Tests Will Be Completed by 900831
ML20043B0391990-05-16016 May 1990
Informs of Current Status of Post Accident Sampling Sys. Program Meets Min Requirements & Fulfills Conditions of Tech Spec 5.15
ML20042G9861990-05-11011 May 1990
Forwards Rev 0 to Interim Operability Criteria (Ioc) Criteria for Performing Safety Analysis for Interim Operability of Piping, Resulting from Discussion at 900306 & 0418 Meetings
ML20042G9571990-05-10010 May 1990
Forwards Suppl to Application for Amend to License DPR-40, Making Administrative Clarification to Chloride Sampling Requirements.Standing Order Procedure S.O.-M-10, Tool Accountability Also Encl
ML20042G9981990-05-10010 May 1990
Forwards Proprietary & Nonproprietary Rev 13 to EPIP-EOF-18, Offsite Radiological Surveys.
ML20042H0021990-05-10010 May 1990
Fowards Fort Calhoun Station Performance Indicators,Mar 1990, Monthly Rept
ML20042G4671990-05-0909 May 1990
Forwards Application for Amend to License DPR-40,changing Chemical & Vol Control Sys
1990-09-07
[Table view] |
Text
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Omaha Public Power District 1623 Hamey Omaha, Nebraska 68102 402/536-4000 April 15, 1983 LIC-83-093 Mr. Robert A. Clark, Chief U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Wash'ing ton , D.C. 20555
Reference:
Docket No. 50-285
Dear Mr. Clark:
Generic Letter 82-33, Supplement 1 to NUREG-0737,
" Emergency Response Capabilities" The subject letter asked all utilities to define their imple-mentation schedules for the requirements identified in that letter. Accordingly, attached is Omaha Public Power Dis-trict's response.
Si _ rely, W. .
fkUb Jones Divis ion Manager Production Operations WCJ/TLP:jmm Attachment cc: LeBoeuf, Lamb,'Leiby & MacRae p 1333 New Hampshire Avenue, N.W. b Washington, D.C. 20036 )
Mr. L. A. Yandell, NRC Senior Resident Inspector 8304190281 830415 PDR ADOCK 05000285 PDR p
45 5124 Employmen h qual Opportunity
m UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
) l Omaha Public Power District .) Docket No. 50-285 (Fort Calhoun Station, )
Unit No. 1) ) ,
AFFIDAVIT
. . . . . being duly sworn, hereby deposes and says that he is Division Manager - Production Operations of Omaha Public Power District; that he.is duly authorized to sign and file with the Nuclear Regulatory Commission the attached response to Generic Letter 82-33; that he is familiar with the con-tent thereof; and that the matters set forth therein are true and correct to the best of his knowledge,-information and belief.
fW
'4. C. Jones DivisNon Manager Production Operations STATE OF NEBRASKA)
) ss COUNTY OF DOUGLAS)
Subscribed and sworn to before me, a Notary Public in and for the State,of Nebraska on this /(n/ day of April, 1983.
7 4ok) yNetaryeus11c 4 sensamerm-sw. won.*
i l J.T. GLEASON
% p My Coma Em July 28,1988 I
-- -, - . , . -.e...,.rr,.. rr.m-,,, .-,,,c.-- ..-.,.e . - - - . --nm--. ,, - - , , , . - - - - ,
Enclosure i.
OMAHA PUBLIC POWER DISTRICT'S RESPONSE TO GENERIC LETTER 82-33 Generic Letter 82-33 forwarded NUREG-0737, Supplement 1, p
which details the Commission's 'osition on 5 TMI related tasks; all related to improved capabilities for responding to plant emergencies. These 5 tasks are:
(1) Implementation of a Safety Parameter Display' System (SPDS). .
(2) Performance of a Detailed Control Room Design Review
( DCRDR) .
(3) Evaluation of Compliance with Regulatory Guide 1.97, Revision 2 (R.G. 1.97).
(4) Implementation of Upgraded Functi'on Oriented Emergency Operating Procedures (EOP's).
(5) Development of Emergency Response Facilities (ERF's) .
The District has reviewed the above requirements and Attach-ments 1 through 5 detail the present status and final com-pletion schedules for each of the 5 tasks. It should be noted that each of these 5 tasks are interrelated to one or uare of the other tasks and, as such, these schedules have been integrated. The District has made significant progress in the development of the SPDS, EOP's, and ERF's and these
_ tasks will be completed concurrently with the 1985 refueling outage. For DCRDR and R.G. 1.97, the initial stages of the planning effort were only recently initiated and will lag the other tasks in full implementation.
l 1
Attachment 1 SAFETY PARAMETERS DISPLAY SYSTEM SCOPE:
The basic hardware. installation and computer programming for Safety Paraneters Display System (SPDS) is currently in pro-gress. The SPDS is part of 2 major modification efforts:
(1) the Emergency Response Facility Computer System (ERFCS) and (2) the Inadequate Core Cooling System (ICCS).
The ERFCS will be the real time data processing system which will present plant parameters to the operator in such a fashion as to be able to determine the safety status of the plant.
The ICCS is being installed in response to Generic Letter 82-28 and consists of 3 major components: (1) the Heated Junction Thermocouple (HJTC) system to monitor reactor ves-sel liquid inventory, (2) accident qualified Core Exit Thermocouples (CET's) for reactor temperature monitoring, and (3) a Qualified Safety Parameter Display System (QSPDS) which acts as a Class lE data processing system for the HJTC, CET's, and other lE signals. The QSPDS, in turn, pro-vides the lE data to the ERFCS via a fiber optic serial data link.
The scope of the project also includes: (1) the install-ation of mineral insulated cable and new electrical pene-trations to link the HJTC and CET's to the control room, (2) cabling necessary to provide plant parameter to the ERFCS and QSPDS, (3) displays of the information in the EOF, TSC, and control room, (4) primary system pressure boundary modi-( fication to accommodate the HJTC probes, and (5) the quali-fled CET's.
PROJECT STATUS:
To date, the following work has been accomplished:
(1) HJTC probe holders are installed in the reactor.
(2) The new incore detectors (CET's) and their modified ICI reactor flanges are installed and operable through the existing plant computer.
(3) Approximately 60% of the mineral insulated cable in containment is installed (100% of the seismic hangers
! are installed).
l l (4) Approximately 75% of the cable outside containment is in place. This cable is approximately 20% terminated.
1-1 1 ,. - ..
i
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(5) The 2 new electrical penetrations are installed in con-tainment. \
l (6) The ERFCS power distribution system is about 65% com-plete.
.(7) The ERFCS signal junction cabinets are installed in the cable spreading room.
(8) The Sigma II computer has been removed and the com-puter room floor core drilled for the ERFCS data acqui-sition system.
(9) The QSPDS panels have been installed in the control -
room.
PROJECT SCHEDULE FOR COMPLETION:
The completion of the project scope is hinged around a suc-cessful factory acceptance test of the ERFCS, its delivery and installation, site testing, and operational availability 1
testing.
The schedule, as provided by the ERFCS vendor, calls for a factory acceptance test (FAT) from May 23, 1983 to June 8, 1983; installation from June 20, 1983 to July 8, 1983; site testing from July 11, 1983 to July 22, 1983; and the oper-ational availability testing from August 8, 1983 to
- February 8, 1984. NOTE: During the 6 month operational availability testing, no hardware or software changes which would impact the computer operation (i.e., the entry of a new program which could cause a software failure) will be permitted.
i For the SPDS to be completed on a schedule which would pro-l vide the earliest possible operation, the operational avail-l ability testing must be complete by the beginning of the 1984 refueling outage (February 27, 1984). This allows only l 3 weeks for contingencies to complete computer installation l and testing. If any slippage were to occur, there may not be enough outage time available in 1984 to accomplish all outage related work necessary for an operable SPDS. Based upon the District's experience, it is normal to allow much more than 3 weeks for contingencies in a year long project;
! thus, we believe the probability of the operational avail-l ability testing being completed prior to the 1984 outage to be extremely low. Accordingly, the District expects the l
SPDS to be completed during the 1985 refueling outage, al-lowing for an operational date of November 30, 1985.
SAFETY ANALYSIS SCHEDULE:
The selection of parameters for the SPDS has been completed
! based upon the present generic Emergency Procedure l
l-2
r Guidelines (EPG's). However, other projects (such as imple-menting the plant specific EOP's or R.G. 1.97) can and are expected to result in changes and/or refinements to this parameter set. The District's ERFCS will allow the flexi-bility to incorporate such changes as the need arises. How-ever, consistent with the present guidance provided in NUREG-0737, Supplement 1, the District intends to proceed with the development of the SPDS based upon the EPG's, without waiting for these other projects to be completed.
By October 31, 1983, the District will provide a safety analysis justifying the set of SPDS parameters presently selected for the SPDS. Any subsequent changes to this parameter set will be evaluated in accordance with the criteria of 10 CFR 50.59. .
TRAINING:
Training on the SPDS will be in at least 2 parts. Part 1 will consist of training on the operation of the SPDS computer (i.e. , how to retrieve information, call up dis-plays, trend points, etc.). This will require each shift and other appropriate emergency response personnel to be trained for 1 week.
The other training will be part of the new emergency pro-cedures. In order to maintain system reliability, several weeks of I&C technician training will be required on both the ERFCS and QSPDS.
VERIFICATION AND VALIDATION:
The physical capabilities of the ERFCS and SPDS will be veri-fled through the operational availability testing and sub-sequent District performance demonstrations. The validation of the SPDS parameter set will be included as part of the V&V effort for the new plant specific EOP's, as detailed in Attachment 4.
1-3
Attachment 2
\
DETAILED CONTROL ROOM DESIGN REVIEW (DCRDR)
The District will develop and implement the DCRDR program along the guidelines provided by the industry-supported Nuclear Task Action Committee (NUTAC) on DCRDR. Currently, the District is developing a draft program plan. The draft plan will be completed by May 30, 1983 and will be used as the specification for selecting a contractor to support the District in implementing the DCRDR.
DCRDR activities and tasks are expected to be integrated with other NUREG-0737, Supplement 1, issues in the following ways:
(1) EOP's - One basis for the DCRDR will be the systems review and task analysis conducted as part of the development'of the plant-specific.EOP's. DCRDR verification of task performance capabilities and validation of control room functions shall be integrated with EOP Verification and Validation (V&V) activities. Procedural modifications / enhancements shall be considered as a solution to identified Human Engineering Deficiencies (HED's).
(2) SPDS - The DCRDR survey and verification of task performance capabilities shall include an evaluation of the SPDS. SPDS enhancements shall be considered as a solution to identified HED's.
(3) R.G. 1.97 - The R.G. 1.97 design packages will require man-machine interface reviews as part of the human factors requirement. CR improvements emanating from the DCRDR shall be integrated with R.G. 1.97 based improvements.
(4) Integrated Training - Recommendations, based on oper-ator interviews and walk-throughs/ talk-throughs of procedures, for improvements resulting from the DCRDR shall be incorporated in training programs. Training shall be considered as solutions to identified HED's.
In planning the implementation of the DCRDR, the District has established the following milestones and completion dates:
Milestone Completion Date Develop Draft Program Plan May 30, 1983 Define Manpower Requirements May 30, 1983 Select Contractor August 15, 1983 2-1
Milestone- Completion Date
- Start Review Sep'hember 1, 1983-Submit Final Program Plan to the NRC October 15, 1983 Review Operation Experience February 1, 1984 Conduct CR Survey April 1, 1984 Verification of Task Capabilities August 1,,1984 Validation of CR Functions October 1, 1984 HED Assessment Februar y 1,1985 Submit Summary Report April 1, 1985 Implementation and V&V of CR improvements have not been 3
scheduled since it is r:ot possible to develop a specific implementation schedule until completion of the review and .
assessment activities. The summary report will contain V&V and implementation schedules for correction of HED's.
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Attachment 3 SCHEDULE FOR IMPLEMENTATION OF REGULATORY GUIDE 1.97, REVISION 2 In accordance with our letter dated June 1, 1981, the District submitted a conceptual design for construction of Emergency Response Facilities (ERF's) and installation of the new ERF computer. In this conceptual design, the District committed to connecting some of the presently available instrumentation to the ERF computer and/or SPDS.
The installation of this ERF computer and the SPDS is in progress and is expected to be completed during the 1985 refueling outage. Several available inputs, including some of the instrumentation installed per the requirements of NUREG-0737, are also in the process of being connected to the ERF/SPDS computer. The operational ERFCS/SPDS will provide indication of selected Fort Calhoun accident monitoring instrumentation; however, a preliminary review of the available inputs indicates some deviations from the recommendations of R.G. 1.97 as they presently exist.
The District plans to continue with the present installation plans and simultaneously do a detailed study to fully identify deviations from R.G. 1.97 requirements. This study will have to be closely coordinated with other NUREG-0737 Supplement I requirements; such as control room design re-views, emergency operating procedures, etc. The schedule for this study is, therefore, dependent upon timely com-pletion of other items.
This study will constitute Phase 1 of R.G. 1.97 imple-mentation and will provide information as requested in section 6.2 of NUREG-0737, Supplement 1. This will also provide justification for any deviations and schedule for upgrading and modifications of the existing instrumentation (Phase 2).
Various steps required for this study and the time required for each step are as follows:
(1) Preparation of the plant specific Types A, B, C, D, and E variable list - This will initially require review of the generic Emergency Procedure Guidelines to prepare a Type A variable list, preparation of review criteria. and the actual review of Types B, C, D, and E variab as to identify deviations from the R.G. 1.97 criterion, environmental qualification, redundancy, instrunent ranges, power source and seismic qualification. With regard to the quality assurance requirements, it is the District's under-standing that for the existing instrumentation, the QA 3-1
requirements applicable at the time of issue of the construction permit or as detailed in the USAR will be applicable. The completion of this step is expected to take approximately 34 weeks.
(2) Justification of deviations - Any deviations from the recommendations of R.G. 1.97 will be resolved by per-forming additional analysis to justify existing equip-ment, proposing Technical Specification or procedural changes or qualifying the existing instrumentation.
If justification ~is not possible, the District will propose modifications .and upgrading if required. This step is estimated to take approximately 20 weeks.
(3) Preparation of the conceptual designs and modifi-cations schedule - In order to propose a realistic schedule for upgrading of the existing instrument-ation, the District plans to do_ a conceptual design to fully define the scope of work and establish equipment delivery schedules. In preparation of the conceptual design, an iterative process will.be used that con-siders changes associated with EOP's, control room de-sign reviews, and the operable ERF/SPDS for proper integration of all requirements. It is expected that this step will take approximately 12 weeks.
(4) Preparation of the final report - The results of the preceding 3 steps will be summarized in a report to be submitted to the NRC. Preparation of this report and the internal reviews are expected to take approxi-mately 16 weeks. The final report will provide inform-i ation as requested in section~6.2 of NUREG-0737, Sup-plement 1, and will be available'for NRC review by April 1, 1985.
, The above schedule is summarized in the attached block diagram (Figure 1).
NUREG-0737, Supplement 1, also calls out a specific ex-ception from R.G. 1.97 related to meteorological instru-mentation. The District has evaluated these revised re-quirements. The results of this evaluation are provided below.
The 110M meteorological tower is equipped with a redundant primary power supply, fed from two separate power sources, and instrumentation. Reliable indication of-the meteor-ological variables (wind speed, wind direction, and atmos-pheric stability) is provided by the tower instrumentation, via various equipment, in the control room. The available instrumentation and the level of redundancy are provided on the attached Table 1. A cross-comparison of the specifi-cations for the currently installed instruments with ones indicated in R.G. 1.97, Revision 2, is also provided in Table 1.
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Real time meteorological data is available in the control room from the plant computer by calling up the specific computer addresses. Historical meteorological data may be accessed by use of a magnetic tape which records one minute scan values from all instruments. Historical data is also available from the control-room's computer log where hourly and 24-hour average data is available. Visual indications
-for wind speed, wind direction,.and delta temperature are provided in the control room to provide real-time data and to immediately detect the failure of data recovery. In fo rm-ation on the meteorological conditions for the site vicinity can also be obtained via voice communication with the National Heather Service.
Meteorological instruments are inspected and serviced at a frequency that ensures an annual 90% joint data recovery for the meteorological variables per Regulatory Guide 1.23. No changes in the existing meteorological monitoring system are proposed as it has been historically prov,iding reliable indi-cations of the meteorological variables. The most recent annual joint data recoveries for 1980, 1981, and 1982 were 94.9%, 99.7%, and 97.6%, respectively.
Therefore, the District presently meets the criteria for the meteorological data. These parameters will be incorporated into the ERFCS for radiological assessments and will be available in the control room, TSC, and EOF.
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SCD(DLLE 10 WEEKS S ' ASSIGN REVIEC .
RESPONSTEFLITY 2____ __ ______ - .---- ..
EST ABLISH REVIEW /
4 -_-----__
DESIGN TEAM p
RETAIN OUTSIDE CONE >LLTANT IF RE0 0 tRESPONSIBLE DEPT. MANAGER) o ESTABLISH REVIEW 12___e _ ___________ __ -_ ,
CRITERIA i,
COMPAhE AVAILd:6LE INSlHUf'.ENT ATION WITH TYPE 3. C.0 APO E R.G.1.97
^ ~~
VARIABLE LIST IN THE AREA 0F REQUNDANCY.RANCE. ACCURACY Are f IINA'LI[E EMERIEtTV- OUALIFICATION
- 24. - _L OPERATING PROCEOURE - - - - - - - . _ _ _ _ _
E0P TEAMP ESTABLISH TYPE A g_, VARIABLE LIST 4
REVIEW TYFE A VARIABLE LIST g 34.
i b i t IhSTRUMENTS FOR INSTRUMENTS FOR VHICH ALL REQUIRE- VHICH ALL REcuIRE-M NTS ARE MET MENTS ARE NOT MET
- 34. . - , , , , , , , , , , , , , , , , , _ _ , , , , _ , , , , , , , _ _ , , , , , , ,
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JUSTIFY THE ADEOUACY OF _ ADDITIONAL EXISTING INSTRUMENTATION ACCIDENT ANALYSIS WITH i,
g PROPOSED PENDING TECH SPEC EQUIPMENT CHANGES ,
y-- CHANGES OUALIFICATION PROPOSE ADDIT,IONAL gp g THE EXISTING 54________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _
t PREPARE CONCEPTUAL DESIGN / ----i - e ESTABLISH MODIFICATION CON 1ROL ROOH I ISPOS/ERF i SCN h E LDESIGN REVIEW,3 JISPLAYg 66 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ , _____ ___ _
PREPARE PRELIMINARY 4 }-
REPORT
- 72. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
4 INTERNAL REVIEWS
- 78. . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
4 FINAL REPORT TO NRC 82.- _ - _ _ _ - - - - _ - _ _ .
REG GUIDE 1.97 IMPLEMENTATION
. SCt(DtAE - PNASE 1
.g _
il 1
_T_ABLE 1 Instrument Specifications, locations and Level of Redundancy l Instrument Location
! Meteorological Parameter Instrument Specification and Level of Redundancy Reg. Guide 1.97 110M Met. Tower Location Quantity l
1
- 1. Wind Direction Azimuth (Degrees) O to 360 0 to 540 110M 1 a
j Accuracy (Deg.) 15 15 45M 1 Damping Ratio 0.4 to 0.6 0.6 10M 2 w
E Distance Cons. (m) f2 1.2
! 2. Wind Speed Range (mph) O to 67 0 to 100 110M 1 l
j Accuracy (mph) 1 0.5 1 0.5 45M 1 Starting Thres. (mph) 1.0 0.9 10M 2 I
- 3. Atmospheric Range (*C) -5 to 10 -5 to 15 110M-10M 3 Stability (Delta Temp) Accuracy (*C) 1 0.15 1 0.1 1
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Attachment 4 SCHEDULE FOR UPGRADED EMERGENCY OPERATING PROCEDURES (EOP'S)
Reference 1 transmitted the Combustion Engineering Owners Group's (CEOG's) latest report and revisions to Emergency Procedure Guidelines (EPG's).
Reference 2 stated that the guidelines contained in CEN-152, Revision 1, are applicable to the Fort Calhoun Station and will serve as the technical guidelines for the development .
of EOP's for the Fort Calhoun Station.
The Dictrict's process for developing EOP's will include the organization of a Procedures Writing Group to translate the technical guidelines contained in CEN-152, Revision 1, into EOP's; the use of workshops to verify the guidelines; the validation of the EOP's; and a training program for the EOP's. The District plans to implement the upgrade of EOP's following a refueling outage. The training for the upgraded EOP's must be completed prior to a refueling outage because the level of participation required of operations personnel in a refueling outage prohibits trnining during the outage.
The District intends to use the Procedures Writing Group to develop the EOP's from the EPG's. This group will consist of plant operations personnel and selected technical support personnel familiar with plant operations, transient re-sponse, and plant design. The product produced by the work-ing group will be the upgraded EOP's. It is estimated that approximately 4 months will be required to develop the new EOP's.
l The District intends to use workshops similar to those used by the CEOG to verify the EOP's. Participants in the work-shop will include Fort Calhoun operations personnel and Dis-trict engineers who are f amiliar with plant design and the transient response of the Fort Calhoun Station. These per-sonnel will not have been involved in the Procedures Writing Group. In addition to considering the EOP's, the workshop participants will also consider the interface between EOP's and the SPDS. The current SPDS displays will be reviewed for their applicability to the EOP's. The product of these l
workshops will be a validated set of EOP's and the associ-l ated SPDS displays. It is estimated these workshops will require 2 months to complete.
The District will perform an EOP validation which will evalu-ate the EOP's for usability and operational correctness.
The District anticipates using control room walkthroughs in this process. It is estimated the validation process will require 2 months to complete.
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The' District currently utilizes'6 operating shifts at the Fcrt Calhoun Station. Each shift is in training 1 week out-of every 6 weeks. It is estimated that 2 weeks of formal training, per individual, will be require ~d for training on the upgraded EOP's. Therefore, 3 months will be required to train all operations' personnel at the Fort Calhoun Station on the upgraded EOP's.
The attached table shows that'a total of 11 months will be required to implement the upgraded EOP's at the Fort Calhoun Station. The Fort Calhoun Station has recently completed a 4 month refueling outage. The next refueling is scheduled to start in late February or early March of 1984. Fort
, Calhoun operations personnel will be at simulator training
- during the months of May and June, 1983 and will not be 1
available at that time to participate in a Procedures Writing Group. The District feels that it is absolutely necessary to have operations personnel in the Procedures Writing Group. Since there are only 9 months available from the time at which the operations personnel complete their simulator training to the start of the 1984 outage, it will not be possible to implement the upgraded EOP's following the 1984 refueling outage.
The next refueling outage is currently scheduled for September of 1985. The upgraded EOP's will be implemented following the 1985 refueling outage in December, 1985.
REFERENCES:
(1) Letter from R. W. Wells, CE Owners Group Chairman, to D. G. Eisenhut, NRC, " Transmittal of CEN-152, Revision 1, Combustion Engineering Emergency Procedure Guide-lines", November 22, 1982.
(2) Letter from W. C. Jones to R. A. Clark (LIC-82-414),
December 30, 1982.
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DEVELOPMENT OF UPGRADED FORT CALHOUN STATION EOP'S Months Required to Complete Total Task Task Months Procedures Writing Group Develops EOP's from EPG's 4 4 Verification Using a Work-shop Process 2 6 -
Validation 2 8 Training 3 11 i
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Attachment 5
\
EMERGENCY RESPONSE FACILITIES (ERF'S)
The ERF's for the Fort Calhoun Station consist of a. Tech-nical Support Center (TSC) and Operations Support Center (OSC) physically located within the plant's security bound-ary and an Emergency Operations Facility (EOF) located at the North Omaha Station 17 miles south of the Fort Calhoun Station. The TSC and portions of the OSC are physically located in the same building which is designed for continued occupation throughout all design basis accidents. With the exception of the data acquisition and radiological assess-ment to be provided by the ERFCS/SPDS, the ERF's are consi-dered fully operational and meet the requirements of NUREG-0737, Supplement 1. As discussed in Attachment 1, the data acquisition capability will be available by November 30, 1985.
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