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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:NRC TO UTILITY
MONTHYEARML20062G6561990-11-19019 November 1990 Forwards Amend 134 to License DPR-40 & Safety Evaluation. Amend Addresses Two Administrative Changes ML20216K0541990-11-14014 November 1990 Forwards Safety Evaluation Denying Request for Exemption from Requirements of 10CFR50,App R for Fire Area 34B for Wide Range Nuclear Power Instrumentation Channels.Required Level of Protection Not Provided ML20062E4641990-11-0909 November 1990 Forwards Insp Rept 50-285/90-42 on 901015-19.No Violations or Deviations Noted ML20058H0551990-11-0101 November 1990 Forwards List of Unimplemented Gsis,Per Generic Ltr 90-04 ML20058C6821990-10-24024 October 1990 Offers No Comment on Annual Exercise Scenario Submitted Via ML20058A3901990-10-19019 October 1990 Advises That Maint Team Reinspection Scheduled for Wks of 901203 & 10.Meetings Will Be Scheduled on 901113-14 in Preparation for Insp.List of Required Matls Encl ML20062B6041990-10-12012 October 1990 Forwards Amend 133 to License DPR-40 & Safety Evaluation. Amend Modifies Tech Spec to Increase Refueling Boron Concentration & Revise Storage Requirements of Spent Fuel Pool Region 2 ML20059N3311990-09-28028 September 1990 Forwards Final SALP Rept 50-285/90-24 for Period of May 1989 - Aug 1990.Actions Discussed in 900726 SALP Mgt Meeting & Util 900827 Response to Initial SALP Rept Considered to Be Responsive to NRC Concerns & Recommendations ML20059M6751990-09-28028 September 1990 Forwards Insp Rept 50-285/90-35 on 900729-0910.No Violations or Deviations Noted ML20059K7061990-09-14014 September 1990 Disagrees W/Position That More Detailed Design & Safety Assessment Using Ipe/Pra Appropriate Framework,Per Generic Ltr 89-19 ML20059K3691990-09-14014 September 1990 Ack Receipt & Review of Changes to Emergency Plan Re Emergency Facilities & Equipment Based on Review of .Proposed Changes Acceptable ML20059J9871990-09-13013 September 1990 Provides Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 901010.W/o Map of Exam Area & Preliminary Instructions to Participant Encl ML20056B4071990-08-20020 August 1990 Forwards Insp Rept 50-285/90-34 on 900730-0803.No Violations or Deviations Noted.Unresolved Items Identified in Paragrphs 2.1 & 4.0 of Encl Insp Rept ML20059A2211990-08-17017 August 1990 Forwards Evaluation of Cen 387-P, Pressurizer Surge Line Thermal Stratification. Info Provided by C-E Owners Group in Ref 1 & 2 Inadequate to Justify Meeting All Appropriate Limits for 40-yr Plant Life ML20058M8071990-08-10010 August 1990 Discusses Closeout of NRC Bulletin 90-001, Loss of Fill-Oil Transmitters Mfg by Rosemount. Util Replaced Four Transmitters Which Fell within Scope of Bulletin During Refueling & Maint Outage ML20058N3711990-08-10010 August 1990 Advises That Programmed Enhancements for Generic Ltr 88-17, Loss of DHR, Acceptable ML20056A5761990-08-0707 August 1990 Forwards Request for Addl Info to Review Alternate Seismic Criteria & Methodologies for Facility ML20056A7551990-08-0606 August 1990 Advises of Concluded Investigation Case 4-87-016 Re Alleged False Welding Records,Violations of Employee Protection & Cheating on Welding Performance Tests.Allegations Unsubstantiated ML20056A1721990-07-30030 July 1990 Advises That Written Licensing Exams Scheduled on 901113 & Operating Licensing Exams Scheduled on 901114 & 15.Licensee Requested to Furnish Ref Matl Listed in Encl 1 by 900917 in Order to Avoid Exam Being Rescheduled ML20056A3461990-07-27027 July 1990 Summarizes 900724 Meeting W/Util in Region IV Ofc Re Changes to Operator Licensing Program ML20055J1461990-07-23023 July 1990 Forwards Insp Rept 50-285/90-30 on 900513-0616 & Notice of Violation.App C Withheld from Public Per 10CFR73.21 ML20055G1791990-07-18018 July 1990 Ack Receipt of Advising NRC of Corrective Actions in Response to Violations Noted in Insp Rept 50-285/90-13. Implementation of Actions Will Be Reviewed During Future Insp ML20055G3931990-07-16016 July 1990 Informs That Financial Info Submitted for 1990 in Util Satisfies 10CFR.140 Requirements ML20055F6841990-07-12012 July 1990 Forwards Initial SALP Rept 50-285/90-24 for May 1989 - Apr 1990 IR 05000285/19900021990-07-0909 July 1990 Ack Receipt of 900507 & 0629 Responses to Violations & Deviations Noted in Insp Rept 50-285/90-02 ML20055G0171990-07-0606 July 1990 Forwards Amend 132 to License DPR-40 & Safety Evaluation. Amend Changes Tech Spec Pages 5-1,5-5,5-8 & 5-9a to Incorporate Title Changes as Result of Reorganization & Partial Relocation of Emergency Planning Dept IR 05000285/19900291990-07-0505 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-285/90-29 ML20055C7901990-06-18018 June 1990 Forwards Insp Rept 50-285/90-26 on 900416-0512.Violations Noted.No Citations Issued for Violations Discussed in Paragraphs 5.a,5.b, & 5.c of Rept ML20055C8051990-06-15015 June 1990 Forwards Insp Rept 50-285/90-25 on 900402-06 & 16-19 & Notice of Violation.Violations Pertain to Inadequate Assessment Aids,Detection Aids,Compensatory Measure & Key Control ML20059M9681990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C4101990-02-23023 February 1990 Advises That 891010 & 1207 Changes to Emergency Plan Reviewed by Emergency Preparedness Staff & Acceptable ML20248C7421989-09-28028 September 1989 Forwards Insp Rept 50-285/89-32 on 890801-31.Noted Violations Not Being Cited to Encourage & Support Util self-identification & Correction of Problems.One Unresolved Item Discussed in Paragraph 7.a of Rept ML20248C4901989-09-22022 September 1989 Forwards Summary of 890828 Enforcement Conference in Arlington,Tx to Discuss Violations Noted in Insp Repts 50-285/89-10 & 50-285/89-31.Attendance List Also Encl ML20247Q6361989-09-21021 September 1989 Forwards Amend 8 to Indemnity Agreement B-67,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements IR 05000285/19890011989-09-19019 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-285/89-01.NRC Will Withdraw Items 3 & 4 If Review of Safety Evaluation Documentation Found to Be Adequate ML20247L2491989-09-18018 September 1989 Advises That 890907 Meeting W/Util Re Status of Plant Safety Enhancement Program Provided for Better Understanding of Progress Util Made in Implementing Program.List of Attendees & Meeting Slides Encl ML20247L6161989-09-0606 September 1989 Advises That 890808 Priority Description & Interim Milestones for Rev of safety-related Procedures & Commitment to Final Completion Date of 901231 Acceptable.Nrc Should Be Notified If Interim Milestones Cannot Be Met ML20247A3151989-08-30030 August 1989 Forwards Final SALP Rept 50-285/89-19 for May 1988 - Apr 1989,summary of 890713 Meeting to Discuss SALP Rept & Util 890817 Response to SALP Rept ML20247B1611989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executives Meeting on 890818 in Arlington,Tx.Topics Discussed Included Improving Communications,Salp Process in Region IV & Enforcement.List of Attendees & Agenda Encl ML20247B4191989-08-29029 August 1989 Forwards Insp Rept 50-285/89-28 on 890701-31.No Violations or Deviations Noted.One Unresolved Item Identified ML20246F0161989-08-25025 August 1989 Forwards Insp Rept 50-285/89-30 on 890724-28.No Violations or Deviations Noted ML20246D5521989-08-23023 August 1989 Discusses Util Response to Generic Ltr 89-08, Erosion/ Corrosion-Induced Pipe Wall Thinning, & Advises That Licensee Maintain,In Auditable Form,Records of Program ML20246E0791989-08-18018 August 1989 Discussess Insp Repts 50-285/89-10 & 50-285/89-23 on 890227-0303 & 0508-10 & Forwards Notice of Violation. Decision Not Reached by NRC Re Failures to Adequately Protect Safeguards Info from Compromises,Per 10CFR73.21 ML20246A0531989-08-17017 August 1989 Forwards Supplemental Safety Evaluation for Rev 4 to Inservice Testing Program for Pumps & Valves,Per Generic Ltr 89-04 ML20245H8901989-08-15015 August 1989 Forwards Safety Evaluation Supporting Util 890215 Response to Generic Ltr 83-28,Item 2.1 (Part 1), Vendor Interface for Reactor Trip Sys Components ML20245K3431989-08-11011 August 1989 Forwards Safety Evaluation Determining That Isolation Devices Qualified & Acceptable for Interfacing Safety & Nonsafety Sys Re Implementation of ATWS Rule 1990-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G9261999-10-15015 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 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 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 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 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) 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 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 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 ML20210P8991999-08-0909 August 1999 Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill 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 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 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 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 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 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 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 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 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 ML20196F4931999-06-24024 June 1999 Discusses 990617 Public Meeting at Dana College,Blair,Ne Re Overview of Pilot Insp Program ML20196D2321999-06-21021 June 1999 Forwards Corrected Cover Ltr for Insp Rept 50-285/99-04. Original Cover Ltr Incorrectly Stated That Rept Contained Two Noncited Violations,When Rept Actually Documented Only One ML20195J2121999-06-14014 June 1999 Ack Receipt of Ltr Dtd 990316,which Transmitted Rev 16B to Site Security Plan,Rev 2 to Safeguards Contingency Plan & Rev 6 to Training & Qualification Plan for Plant,Under Provisions of 10CFR50.54(p) IR 05000285/19990041999-06-11011 June 1999 Corrected Ltr Forwarding Insp Rept 50-285/99-04 on 990425-0531.Insp Determined That One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation, Consistent with App C of Enforcement Policy ML20195J2481999-06-11011 June 1999 Forwards Insp Rept 50-285/99-04 on 990425-0531.Violations Identified & Being Treated as Noncited ML20195G3141999-06-10010 June 1999 Ack Receipt of & Encl Objectives for Facility Emergency Plan Exercise,Scheduled for 990810 ML20195E8391999-06-0909 June 1999 Ack Receipt of Transmitting Changes to Licensee Emergency Plan,Rev 14 & Emergency Plan Implementing Procedure OSC-1 Under Provisions of 10CFR50,App E,Section IV ML20207G4741999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station EP Implementing Procedure EPIP-OSC-1, Emergency Classification,Rev 31,under Provisions of 10CFR50, App E,Section V ML20207G4631999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station Ep,App B,Rev 4,under Provisions of 10CFR50,App E,Section V.No Violations Identified During Review ML20207G2981999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station Radiological Er Plan,Section E,Rev 22,under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required Due to Determination That Effectiveness Unchanged ML20207G4661999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station EP Implementing Procedure EPIP OSC-1, Emergency Classification,Rev 30,under Provisions of 10CFR50, App E,Section V ML20195G3621999-06-0808 June 1999 Ack Receipt of ,Which Transmitted Changes to Fort Calhoun Station Emergency Plan,App A,Rev 15,under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required ML20207G3401999-05-27027 May 1999 Informs That NRC Held Planning Meeting on 990511 for Fort Calhoun Station to Identify Insp Activities at Facility for Next 6 to 12 Months.Informs of NRC Planned Insp Activities & Offers Licensee Opportunity to Provide Feedback ML20207A9041999-05-24024 May 1999 Informs That NRR Reorganized,Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Was Created. Reorganization Chart Encl ML20206U6331999-05-18018 May 1999 Forwards Insp Rept 50-285/99-03 on 990314-0424.Four Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20206L4151999-05-10010 May 1999 Forwards SE of OPPD Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20206H4471999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key,Encl for Info.Without Encl ML20206E7201999-04-28028 April 1999 Responds to Meeting Conducted 990419 in Fort Calhoun,Ne Re Results of PPR Completed 990211.Addl Topics Discussed Included New Assessment Process & Upcoming Actions Planned in Response to Y2K Concerns ML20205Q5671999-04-15015 April 1999 Forwards Amend 190 to License DPR-40 & Safety Evaluation. Amend Revises TS 5.2.f & TS 5.11.2 to Change Title of Shift Supervisor to Shift Manager ML20205J2751999-04-0202 April 1999 Forwards Insp Rept 50-285/99-02 on 990131-0313.No Violations Noted.During Insp,Licensee Conduct of Activities at Fort Calhoun Station Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices ML20205A7191999-03-19019 March 1999 Informs That on 990211 NRC Staff Completed PPR of Fort Calhoun Station.Review Was Conducted for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20207K6151999-03-11011 March 1999 Forwards Insp Rept 50-285/99-01 on 990208-26.One Noncited Violation Was Identified ML20207E8691999-03-0303 March 1999 Forwards Correction to Amend 188 to License DPR-40 for Plant,Unit 1.Administrative Error,Three Pages of TSs Contained Errors,An Incorrect Page Number,Missing Parenthesis & Misspelled Words ML20203F2041999-02-11011 February 1999 Informs That During 990208 Telcon Between Mc Ralrick & J Pellet & T Stetka,Arrangements Were Made for Administration of Licensing Examinations at Fort Calhoun Station for Week of 991018 1999-09-07
[Table view] |
Text
,
May-7, 1985 Docket No. 50-285 DISTRIBUTION:
' N PMKreutzer NRC-PDR ACRS +10 Mr. R. L. Andrews . ORB #3 RDG . Gray' File Division Manager - Nuclear Production HThompson TBournia Omaha:Public Power District 0 ELD JKramer 1623.Harney Street EJordan Omaha, Nebraska 68102 BGrimes JPartlow
Dear Mr. Andrews:
' EGTourigny
SUBJECT:
-DRAFT TECHNICAL EVALUATION REPORT (TER)-FOR-SALEM ATWS ITEM 1.2 (GENERIC LETTER 83-28)
Re: Fort Calhoun Station, Unit 1 The staff has completed a~ preliminary review to assess the completeness and adequacy of licensee responses to Generic Letter 83-28 Item 1.2. For the Fort Calhoun Station, your' response was found to be incomplete in two of the areas evaluated.
-The encl osed TER provides a technical evaluation representing the staff's initial judgment of the areas evaluated. Pen and ink changes have been made to the TER?by your project manager to make the wording consistent with our approach. -
In~ order to preserve our present review schedule, we would appreciate your cooperation in obtaining additional information that will pennit us to complete our review. .It would' appear that the needed information on your facility could be.obtained by telephone conference within one week of your receipt of the' DRAFT TER. Your project manager will be working with you to arrange an acceptable time to conduct the necessary conference calls.
~The reporting and/or recordkeeping requirements contained in this letter affect' fewer than 10: respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, i
e i
g 53g g g$ $PDR 85 James R. Miller, Chief p Operating Reactors Branch #3 Division of Licensing
Enclosure:
DRAFT TER on Salem
.ATWS Item 1.2 cc w/ enclosure See next page _
, ORBf QL - ORB #3: Dig 3r.r[ 4 ORf#3:DL
.P ter EGTourigriy:c d gb1RMiller 5/ 85 5/ 7 /85 (5/}/85
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SAIC-85/1515 I
- 1 i
REVIEW OF LICENSEE AND APPLICANT RESPONSES TO NRC GENERIC LETTER 83-28 (Required Actions Based on Generic Implications of i
Salem ATWS Events). Item 1.2
" POST-TRIP REVIEW: DATA AND INFORMATION CAPABILITIES" FOR FORT CALHOUN STATION, UNIT 1 (50-285)
. Technical Evaluation Report Prepared by Science Applications International Corporation 1710 Goodridge Drive McLean, Virginia 22102 Prepared for U.S. Nuclear Regulatory Commission Washington. D.C. 20555 Contract No. NRC-03-82-096
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FOREWORD This report contains the technical evaluation of the Fort Calhoun Station, Unit I response to Generic Letter 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events) Item 1.2 " Post Trip Review:
Data and Information Capabilities."
For the purposes of this evaluation, the review criteria, presented in part 2 of this report, were divided into five separate categories. These are:
, 1. The parameters monitored by the sequence of events and the time history recorders,
- 2. The performance characteristics of the sequence of events recorders,
- 3. The performance characteristics of the time history recorders,
- 4. The data output format, and
- 5. The long-term data retention capability for post-trip review material.
All available responses to Generic letter 83-28 were evaluated. The plant for which this report is applicable was found to have adequately responded to, and met, categories 2, 3 and 4. ,a The report describes the specific methods used to determine the cate6 gorization of the responses to Generic Letter 83-28. Since this eva ation report was intended to apply to more than one nuclear power plant s cifics regarding how each plant met (or failed to meet) them are not presented. Instead, the evaluation presents a categorization of the responses according to which categories of Maare satisfied and which are not. The evaluations are based on specific criteria (Section 2) derived from the requirements as stated in the generic letter, w cd'h
. TABLE OF CONTENTS Section Page Introduction. . . . . . . . . . . . . . . . . . . . . . . . . I
- 1. Background. . . . . . . . . . . . . . . . . . . . . . . . . . 2
- 2. Review Criteria . . . . . . . . . . . . . . . . . . . . . . . 3
- 3. Evaluation. . . . . . . . . . . . . . . .-. . . . . . . . . . 8
- 4. C'onclusion. . . . . . . . . . . . . . . . . . . . . . . . . . 9
- 5. Re fe re nc e s . . . . . . . . . . . . . . . . . . . . . . . . . . 10
- 4. So rparsau roc.mr.u.T t%a TeLecoa - - - - - -- II
INTRODUCTION te
. SAIC has reviewed the,rrerg'ssubmittals prepared in response to 83-28, item 1.2 " Post-Trip Review:
- Data and Information Capability".
The submittals (see references) contained sufficient information to determine that the data and capabilities at this plant are acceptable in the following areas.
e The sequence-of-events recorder (s) performance charac-teristics, o
The time history recorder (s) performance characterfs-tics. -
e The output format of the recorded data.
However, the data and information capabilities, as described in the submittal, either fail to meet the review criteria or provide insufftetent information to allow determination of the adequacy of the data and information capabilities in the following areas.
e The parameters monitored by both the sequence-of-events and time history recorders.
e The long-term data retention, record keeping, capa-bility.
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- 1. Background
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On February 25, 1984, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal from the reactor protection system.
This incident occurred during the plant startup and the reactor was tripped manually by the operator about 30 seconds after the initiation of the automatic trip signal. The failure of the circuit breakers has been determined to be related to the sticking of the under voltage trip attachment.
Prior to this incident; on February 22, 1983; at Unit 1 of the Salem Nuclear Power Plant an automatic trip signal 4 was generated based on steam generator low-low level during plant startup.
In this case the reactor was tripped manually by the operator almost coinci-dentally with the automatic trip. At that time, because the utility did not have a requirement for the systematic evaluation of the reactor trip, no investigation was performed to determine whether the reactor was tripped
' automatically as expected or manually. The utilities' written procedures required only that the cause of the trip be determined and identified the responsible personnel that could authorize a restart if the cause of the trip is known.
Following the second trip which clearly indicated the problem with the trip breakers, the question was raised on whether the circuit breakers had functioned properly during the earlier incident. The
' most useful source of information in this case, namely the sequence of events printout which would have indicated whether the reactor was tripped automatically or manually during the February 22 incident, was not retained after the incident.
Thus, no ju.dgment on the proper functioning of the trip system during the earlier incident could be made.
Following these incidents; on February 28, 1983; the NRC Executive Director for Operations (EDO), directed the staff to investigate and repo.rt on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant.' The results of the staff's inquiry into the generic implications.of the Salem Unit incidents is reported in NUREG-1000, " Generic j
Implications of ATWS Events at the Sales Nuclear Power Plant." Based on the
- results of this study, a set of required actions were developed and included i
in Generic Letter 83-28 which was issued on July 8,1983 and sent to all i
. licensees of operating reactors, appif cants for operating license, and construction permit holders. The required actions in this generic letter consist of four categories. These are:
(1) Post-Trip Review, (2) Equipment 2
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Classification and Vender Interface. (3) Post Maintenance Testing, and (4)
Reactor Trip System Reliability Improvements.
The first required action of the generic letter, Post-Trip Reviiw, is the subject of this TER and consists of action item 1.1 " Program Description and Procedure" and action item 1.2 " Data and Information Capcbility." In the next section the review criteria used to assess the adequacy of the utilities' responses to the requirements of action item 1.2 will be discussed.
- 2. - Review Criteria The intent of the Post Trip Review requirements of Generic Letter 83-28 is to ensure that the licensee has adequate procedures and data and information sources to understand the causbnd progression of a reactor trip. This understanding should go beyond a# simple identification of the .o course of the event. It should include the capability to determine the root cause of the reactor trip and to determine whether safety limits have been exceeded and if so to what extent. Sufficient information about the reactor
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trip event should be available so that a decision on the acceptability of a reactor restart can be made.
The following are the review criteria developed for the requirements of Generic Letter 83-28, action item 1.2:
The equipment that provides the digital sequence of events (50E) record and the analog time history records of an unscheduled shutdown should pro-
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vide a reliable source of the necessary information to be used in the post trip review. Each plant variable which is necessary to determine the cause(s) and progression of the event (s) following a plant trip should be monitored by at least one recorder Quch as a sequence-of-events recorder or a plant process computer for digital parameters; and strip charts, a plant process computer or analog recorder for analog (time history) variables).
Each device used to record an analog or digital plant variable should be described in sufficient detail so that a determination can be made as to whether the following performance characteristics are met:
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e i Each sequence-of-events recorder should be capable of detecting and recording the sequence of events with a sufficient time discrimination capability to ensure that the time responses..asso-clated with each monitored safety-related system can be ascer- i tained, and that a determination can be made as to whether the time response is within acceptable Ifmits based on I - FSAR Chapter 15 Accident Analyses. The recommended guideline for the SOE time discrimination is approxi-mately 100 usec.
If current SOE recorders do not have this time
{ discrimination capability the licensee or applicant should show that the current time discrimination capability is sufficient.for an adequate reconstruction of the course of the reactor trip. As
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a minimum this should include the ability to adequately recon-struct the accident scenarios presented in Chapter 15 of the plant FSAR.
e Each analog time history data recorder should have a sample inter- )
val small enough so that the incident can be accurately reconstructed following a reactor trip. As a minimum., the i
licensee or applicant should be able to reconstruct the course of the accident sequences evaluated in the accident analysis of the plant FSAR (Chapter 15). The recommended guideline for the sample interval is 10 sec. If the time history equipment does not meet this guideline, the licensee or applicant should show that the current time history capability is sufficient to accurately recon-
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struct the accident sequences presented in Chapter 15 of the FSAR. '
o
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To support the post trip analysis of the cause of the trip and the proper functioning of involved safety related equipment, each analog time history data recorder should be capable of upda~ ting and retaining information from approximately five minutes prior to the trip until at least ten minutes after the trip.
o The information gathered by the sequence-of-events and time history data collectors should be stored in a manner that will allow for retrieval and analysis. The data may be retained
~ in either hardcopy (computer printout, strip chart output, etc.)
or in an accessible memory (magnetic disc or tape). This i
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._r. r __ .,.. _ . , . . _ . . ~ ~ . . _ , _ _ _ . _ _ _ . - - . . _ _ , . _ _ _ _ . _ _ . , - , , , . - , . _.____y_,.. __ ,
j) information should be presented in a readable and meaningful
[ format, taking into consideration good human factors practices (such as those outlined in NUREG-0700). -
t e
All equipment used to record sequence of events and time history information should be powered from a reliable and non-interruptible power source. The power source used need not be i
safety related.
The sequence of events and time history recording equipment should
) monitor sufficient digital and analog parameters, respectively, to assure
, that the course of the reactor trip can be reconstructed. The parameters monitored should provide sufficient information to determine the root cause of the reactor trip, the progression of the reactor trip, and the response of the plant parameters and systems to the reactor trip. Specifically, all 3
input parameters associated with reactor trips, safety injections and other safety-related systems as well as output parameters sufficient to record the
- proper functioning of these systems should be recorded for use in the post trip review.
j The parameters deemed necessary, as a minimum, to perform a post-trip review (one that would determine if the plant remained within its design envelope) are presented on Tables 1.2-1 and 1.2-2. If the appli-cants' or Itcensees' SOE recorders and time history recorders do not monitor all of the parameters suggested in these tables the appitcant or Itcensee i 4
should show that the existing set of monitored parameters are sufficient to
' establish that the plant remained within the design envelope for the appro-priate accident conditions; such as those analyzed in Chapter 15 of the plant Safety Analysis Report.
Information gathered during the post trip review is required input for future post trip reviews. Data from all unscheduled shutdowns provides a valuable reference source for the determination of the acceptability of the plant vital parameter and equipment response to future unscheduled shut-downs.
It is therefore N that information g gathered during all post tr.ip reviews be maintained in an accessible manner for the 1tfe of the plant.
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Table 1.2-1. PWR Parameter List '
' ~
SOE Time History '
' Recorder Recorder Parameter / Signal 3
(il x Reactor Trip i
(1) x Safety Injection x Containment Isolation (1) x Turbine Trip x Control Rod Position (1) x x Neutron Flux, Power x K Containment Pressure (2) Containment Radiation x Containment Sump Level (1) x x Primary System Pressure (1)x x Primary System Temperature (1) x Pressurizer Level .
(1) x Reactor Coolant Pump Status (1) x x Primary System Flow (3) Safety Inj.; Flow. Pump / Valve Status x MSIV Position x x Steam Generator Pressure (1) x x Steam Generator Level (1) x x Feedwater Flow (1) x x . Steam' Flow (3) Auxiliary Feedwater System; Flow, Pump /Value Status x AC and DC System Status (Bus Voltage) x Diesel Generator Status (Start /Stop, On/Off) x PORY Position (1.): Trip parameters
.(2): Parameter may be monitored by either an SOE or time history recorder.
.(3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
6
. '. l Table 1.2-2. BWR Parameter List SOE Time History
- Recorder Recorder Parameter / Signal
.l x Reactor Trip x Safety Injection ,
x Containment Isolation x Turbine Trip x Control Rod Position x (1) x Neutron Flux, Power
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x (1) Main Steam Radiation
'(2) Containment (DryWell) Radiation x (1) x Drywell Pressure (Containment Pressure)
(2) Suppression Pool Temperature x (1) x Primary System Pressure x(1) x Primary System Level x MSIV Position x (1) Turbine Stop Valve / Control Valve Position x Turbine Bypass Valve Position x Feedwater Flow x- Steam Flow (3) Recirculation; Flow. Pump Status x(1) Scram Discharge Level x (1) ,
Condenser Vacuum x AC and DC System Status (Bus Voltage)
(3)(4) Safety Injection; Flow. Pump / Valve Status x Diesel Generator Status (On/Off, Start /Stop)
(1): Trip parameters.
(2): Parameter may be recorded by either an SOE or time history recorder.
(3): Acceptable recorder options are: (a) system flow recorded on an SOE ,
recorder (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder. -
(4): Includes recording of parameters for all applicable systems from the following: HPCI, LPCI, LPCS, IC, RCIC.
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- 3. Evaluation M
The parameters identified in part 2 of this report as a part of the review criteria are those deemed gMo perform an adequate post-trip review. The recording of these parameters on equipment that meets the guidelines of the review criteria will result in a source of information that can be used to determine the cause of the reactor trip and the plant response to the trip, including the responses of important plant systems.
The parameters identified in this submittal as being recorded by the
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sequence of events and time history recorders do not correspond to the parameters specified in part 2 of thi:: report.
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The information provided in the submittal indicates that the equipment used to monitor the digital and analog parameters meets the minimal requirements set forth in part 2 of this report. The sequence of events and analog time history recorders are powered from a non-interruptable power supply. The monitoring characteristics are all within the guidelines of the review criteria. -
The data and information recorded for use in the post-trip review should be output in a format that allows for ease of identification and use of the data to meet the review criterion that calls for information in a readable and meaningful format. The information contained in this submittal indicates that this 6 is met.
M _A The data and information used during a post-trip revi tw should be retained as part of the plant files. This information could prove useful during future ' post-trip reviews. Therefore one 6' presented in part 2 of this report is that information used during a post-trip review be maintained in an accessible manner for the life of the plant. Information contained within this submittal does not indicate that this criterion will be met.
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- 4. Conclusion The information supplied in response to Generic Letter 83-28 indicates that the current post-trip review data and information capabilities are adequate in the following areas:
- 1. The SOE recorders meet the minimum performance characteristics. l
- 2. The time history recorders meet the minimum performance character-istics. l
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3 The recorded data is output in a readable and meaningful fomt.
The information supplied in response to Generic Letter 83-28 does not indicate that the post-trip review data and information capabilities are ;
adequate in the following areas:
- 1. As described in the submittal, sufficient analog and digital parameters are not recorded for use in the post-trip review.
- 2. The data retention procedures, as desrribed in the submittal, may not ensure that the information recorded for the post-trip review is maintained in an accessible manner for the, life of the plant.
Ma rk It is possible that the current data and information capabilbes at this
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nuclear power plant are adequate to meet the intentP of these 6, but were not completely described. Under these circumstances, the licensee should provide an updated, more complete, description to show in more detail the data and information capabilities at this nuclear power plant. If the information provided accurately represents all current data and information capabilties, then the licensee should either show that the current post trip review data and information capabilities are adequate to meet the intent of the criteria in part 2 of this report, or detail future modifications that would enable the licensee to meet the intent of the evaluation criteria.
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REFERENCES NRC Generic Letter 83-28. " Letter to all licensees of operating reactors, applicants for operating license, and holders of construction i'
permits regarding Required Actions Based on Generic Implications of Salem ATWS Events." July 8, 1983.
NUREG-1000. Generic Implications of ATWS Events at the Salem Nuclear Power Pht April 1983.
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Letter from W.C. Jones Omaha Public Power District, to D.G. Eisenhut, NRC, dated November 4,1983, Accession Number 8311080428 in response to Generic Letter 83-28 of July 8,1983, with attachment.
Omaha Public Power District Response to Generic Letter 83-28 dated November 4, 1983.
Letter from R.L. Andrews . Omaha Public Power District, to J.R. Miller, NRC, dated November 16, 1984 Accession Number 8411260365 providing additional information in response to Generic Letter 83-28, with e attachments.
4
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,9.,,.. --.-,. .-,-.. 7,--, . - ,-s& e---,m-- + , , v>--
SCff*C2M> peremsser % wou Fort Calhoun
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1.
Parameters recorded: Unsatisfactory See attached table for discrepancies.
2.
SOE recorder' performance characteristics:
Satisfactory Plant process computer:
interruptible power supply 16.6 msec time discrimination with a non-3.
. Time history recorders performance characteristics:
Satisfactory Strip charts:
monitoring of parameters meets intent of perfor tics requirements 4.
1 Data output format: Satisfactory SOE data output includes time event descriptor and sensor channe Analog data output in strip chart forms meets requirements 5.
Data retention capability: Unsatisfactory Data is retained but for an unspecified period of time.
0 4
\\
/) M M PWR Parameters for Post Trip Review (circled parameters are not recorded)
SOE Time History ~
Recorder Recorder _ Parameter / Signal
- 6) x Reactor Trip (1) x Safety Injection x
Containment Isolation (1) x Turbine Trip x
Control Rod Position (1) x x
@ Neutron Flux, Power K Containment Pressure
"@ Containment Radiation x Containment Sump Level (1)(3)
Primary System Pressure (Vessel Pressure, (1)x Pressurizer Pressure) x Primary System Temperature (1)x Pressurtzer Level (1)x '
Reactor Coolant Pump Status (1) x 4
@ Primary System Flow Safety Inj.; Flow. Pump / Valve Status 8x x
MSIV Position x
Steam Generator Pressure (1) @ Steam Generator Level (1)
(1)
@ Feedwater Flow x Steam Flow
- Auxiliary Feedwater System; Flow.
Pump /Value Status x
AC and DC System Status 8x x
Diesel Generator Status POW Position (1):
Trip parameters; (depending pressurizer or primary pressure is a trip parameter on plant).
(2):
(3): Acceptable recorder options are: Parameter may be monitored by eith (a) reactor vessel pressure recorded on both an SOE and time history recorder, or (b) pressurizer pressure (4): recorded on both an SOE and time history recorder.
Acceptable recorder options are: (a) system flow recorded on an SOE equipment status recorded on an SOE recorder. recorder, (b) syst Ib
Ft. Calhoun Harry H. Voigt, Esquire LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, DC 20036 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68023 Metropolitan Planning Agency ATTN: Dagnia Prieditis 7000 West Center Road Omaha, Nebraska 68107 Mr. Larry Yandell U.S. NRC Resident Inspector Post Office Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations .
C-E Power Systems 7910 Woodmont Avenue Bethesda, Maryland 20814 Regional Administrator USNRC, Region IV Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 P
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