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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments LIC-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 ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants. ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. 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 ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs 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-99-0088, 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-99-0085, 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 ML18066A6331999-09-0202 September 1999 Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant 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 ML18066A6261999-08-26026 August 1999 Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995 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 ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML18066A6111999-08-13013 August 1999 Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors 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 ML18066A5881999-07-30030 July 1999 Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS ML18066A5921999-07-30030 July 1999 Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants. ML18066A5971999-07-30030 July 1999 Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments ML20210G8351999-07-29029 July 1999 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR 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-99-0040, 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 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 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 ML20058G8921990-11-0707 November 1990 Forwards Insp Repts 50-155/90-20 & 50-255/90-20 on 900925-28 & 1015-19.Violations 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 ML20059M6751990-09-28028 September 1990 Forwards Insp Rept 50-285/90-35 on 900729-0910.No Violations or Deviations Noted 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 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 ML20059G5461990-09-0404 September 1990 Discusses 900816 Site Visit Re Const Activities Requiring Security Force Compensatory Measures & Security Plan 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 ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date 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 ML20056A4981990-08-0101 August 1990 Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls 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 ML20055J4351990-07-23023 July 1990 Ack Receipt of 900702 Transmittal of Rev 26 to Physical Security Plan.Estimated Start & Completion Dates for Each Mod Project & Compensatory Measures Requested within 30 Days After Receipt of Ltr 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 ML20055F2271990-07-0606 July 1990 Forwards Physical Security Insp Rept 50-255/90-16 on 900618- 22 & 25.No Violations Identified 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 ML20059M9181990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20059M9681990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) 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 IR 05000255/19890211989-09-27027 September 1989 Forwards Safety Insp Rept 50-255/89-21 on 890718-0831.No Violations Noted ML20248C9321989-09-26026 September 1989 Advises That 890823 Rev 23 to Security Plan Meets Provisions of 10CFR50.54(p) & Acceptable.Encl Withheld (Ref 10CFR73.21) 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 ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu 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 ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20247K2231989-09-11011 September 1989 Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe ML20247E3371989-09-0707 September 1989 Forwards Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Records Retention for Radiological Effluent Monitoring & ODCM 1990-09-04
[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 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 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 ML20210G8351999-07-29029 July 1999 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR 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 ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 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 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 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 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 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 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 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 1999-09-07
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ - _ - - - _ _
i l
l DISTRIBUT10th , , ,
l Docket File Glainas ~
j NRC PDR .~ ~ UTondi ,.
L PDR JBurdoin .
l Docket h'o.: 00-285 ORBf4 Rdg ; [ ,'T l
RReid ~
1 RIngram [
l PErickson . . ,_
i MConner Omaha Public Power District Attorney, OELD [ _ [.
l ATTN: Mr. Theodore E. Short . OI&E(3) . ,,,
l Division Manager - Prcduction DEisenhut , , _,
Operations TERA, DSB l _ _ ,
l 1623 Harney Street JRBuchanan , ,
Onaha, !;ebraska 68102 ACRS (16) , ,,
TCarter . ,
Centlemen: Gray File , ,
~
On August 2,1970, representatives frou utilities using Combustion l Engir.cering (CE) HSSS and from CE met in Bethesda, liaryland to discuss the action requirements in the event of Reactor Protection System (RPS) channel inoperability. Enclosure 1 15 the minutes of this meeting. The meeting was held to clarify our position en this subject as presented in our letter dated December 7,1977 and to gain an understanding of your position as indicated in your response cated January 31, 1978. This same subject had been discussed pre-viously on March 16, 1976.
In our previous correspondence, we requested that you subott an app 11-cation for license amendment to change the Ft. Calhoun Technical Specifications (TS) Section 2.15 to require inoperable RPS channels to be placed in the " tripped" status within one hour af ter Deing ceclared inoperable. We further stated that you could request that we under-take a specific facility review of your RPS to cetermine the suitabil-ity of operating the RPS in a two-out-of-three logic. Your response f requested such a specific facility RPS review and we propose that the Ft. Calhoun RPS review be schedule 3for the rnonth of Hovember 1978.
The exact date wi'l tv macinated through your Operating Reactor Branch Project hanager (ORPH). Enclosure 2 is the PPS review items that will be of interest to our review team. .
As you know, our staff has conducted the RPS review at the Calvert Cliffs and St. Lucie units. A copy of the resultant Safety Evaluation for St. Lucie, presenting the finding of the RPS review (pages 3 to 5),
is provioed for your int'ornation as Enclosure 3. Our conclusion was l
l 4
8709150148 780910 PDR ADDCK 05000255 P PDR y ['
1 l }
Onaba Public Power District l K.
l that allowing indefinite bypass of one of the four. RPS is not i' 1
justified, but since the four channel CE systen does.have sone independence, bypassing for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> duritsg test 1ng or maintenance l of one_ RPS channel is justified.
As an alternative to the onsite IRC review of your'RPS, we will consirter issuance of the Calvert Cliffs and St. Lucie type TS
(
of your RPS if you provice an application including documentation
. of your RPS sinilarity to those of Calvert Cliffs and St. Lucie. Any
- such application'should be submitted within 45 days of the date of this letter.
Sincerely, Robert W. Reid, Chief .
Operating Reactors Branch #4 Division of Operating Reactors Enlosbres:
- 1. fleeting Suanary
- 2. Review Item
- 3. Safety Evaluation 3
cc w/encit;sures: See next page l
i- I Y
I l
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DISTRIBUTION: '
- Docket File TJCarter NRC PDR- Gray File (ORB #2) '
L PDR JBurdoin i Docket No.: 50-255 ORB #4'Rdg' DTondi RReid Glainas
- RIngram 4 ELConner RSilver l Consumers Power Company ACtorney, OELD ATTH: fir. David 81xel DZiemann Nuclear Licensing Administrator HSmith 212. West liichigan Avenue OI&E'(3)
Jackson, flichigan 4';201 DEisenhut TERA, DSB i Gentlemen: ACRS (16)
JRBuchanan On August 2,1978, representatives from utilities using Combustion Engineering (CE) NSSS and from CE met in Bethesda, fieryland to discuss the action requirements in the event of Reactor Protection System (RPS) channel inoperability. . Enclosure 1 is the minutes of this meeting. The meeting was held to clarify our position on this subject as presented in our letter dated January 18, 1978 and to gain an understanding of your position as indicated in your response dated Harch 21, 1978. This same subject had been discussed pre-vlously on flarch 16, 1976.
In our previons correspondence, we requested that you submit an appli-cation for license amendment to change the Palisttes l Technical Specifications (TS) Section 3.17 to require inoperable RPS channels to be placed in the " tripped" status within one hour after being declared inoperable. We further stated that you could request that we undertake a specific facility review of your RPS to determine the~ suitability of operating the RPS in a trio-out-of-three logic.
Your response requested such a specific facility RPS review and we propose that the Palisades RPS review be scheduled for this month. {
The exact date will be coordinated through your Operating Reactor {
1 Branch Project flanager (ORPil). Enclosure 2 is the RPS review 1tems that will be of interest to our review team.
1 j
As you know, our staff has conducted the RPS review at the Calvert Cliffs and St. Lucie units. A copy of the resultant Safety Evaluation fcr St. Lucie, pr.:sonting the finding of the RPS review (pages 3 to 5),
is provided for your infomation at, Enclosure 3. Our conclusion was i
, ff$&~A~k~ &
i
(
L_-_ _ - .
p.
, #" f ur Consumers Power Company l l .
! that allowing indefinite bypass of one of the four P.PS is not i justified, but since the four channel CE system does have some '
independence, bypasting for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during testing or maintenance of one RPS channel is justified.
As an alternative to the onsite flRC review of your RPS, we will consider issuance of the Calvert Cliffs and St. Lucie type TS of your RPS if you provide an application including documentation '
of your'RPS sisilarity to thos? of Calvert Cliffs and St. Lucie. Any such application should be submitted within 30 days of the date of this letter.
i Si ncerely,
}
I i
, Dennis L. Ziemann, Chief l Operating Reactors Branch #2
! Division of Operating Reactors Enlosures:
- 1. Deeting Sunnary
- 2. Review Iten
- 3. Safety Evaluation cc w/ enclosures:, See next page E
I 4
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Docket File Glainas ;
, NRC PDR DTondi i L PDR JBurdoin !
Rdg !
' Docket No.: 50-336
! RIngram ENHHMMX ELConner Northeast Nuclear Energy Company Attorney, OELD ATTN: Mr. W. G. Counsil, Vice President 01&E (3) ,
fJuclear Engineering & Operations DEisenhut P. O. Box 270 ACRS (16)
Hartford, Connecticut 06101 B ha an Gentlemen: TJCarter ,
Gray File en August 2,1978, representatives from utilities using Combustion Engineering (CE) NSSS and froni CE met in Bethesda, Maryland to discuss the action requironents in the event of Reactor Protection System (RPS) channel inoperability. Enclosure 1 is the minutes of this meeting. The meeting was held to clarify our position on this subject as presented in our letter dated August 3,1977 and to gain an understanding of your position as indicated in your response dated St.ptember 21, 1977. This same subject had been discussed pre-viously on Marcn 16, 1976.
4 In our previous correspondence, we requested that you sebsit an appli-cation for license amendment to change the Hillstone, Unit No. 2 Technical Specifications (TS) Section 3.3.1.1 to require inoperable RPS channels to be placed in the "trippeo" status within one hour af ter being declared inoperable. We further stated that you could request that we under-take a specific facility review of your RPS to determine the suitabil- I ity of operating the RPS in a two-out-of-three logic. Your response '
requested such a specific facility RPS review and we propose that the Hillstone, Unit 2 RPS review be scheduledfor the month of October 1978.
l The exact date will be coordinated through your Operating Reactor Branch Project Manager (ORPM). Enclosure 2 is the RPS review items that will l be of interest to our review team.
I i
As you know, our staff has conducted the RPS review at the Calvert Clif fs and St. Lucie units. A copy of the resultant Safety Evaluation for St. Lucie, presenting the finding of the RPS review (pages 3 to 5),
l 1s provided for your intoraation as Enclosure 3. Our conclusion was l
/-
f, ja A gh?" ,
49lM" Hortheast Huclear Energy Co.- .2-that allowing, indefinite bypass of:one of thel four' RPS is' not
. justified but since the four channel CE system does have some.
independence, bypassing for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />' during testing or maintenance of one RPS channe1 Lis justified.
i As an alternative' to the onsite NRC' review of your RPS. .we will consider issuance of the Calvert Cliffs and St. Lucie type TS of your'RPS if you provide-an application including documentation
'of.ynur RPSl similarity to those of Calvert Cliffs and St. Lucie. Any
-3 such application should be submitted within 45 days of the date of this letter.
Sincerely, ,
1 J
l Robert 14. Reid, Chief
. Operating Reactors Branch #4 Division of. Operating . Reactors j 3
l Enlosures.
- 1. 11eeting Summary >
- 2. Review iteu l
- 3. - Safety Evaluation i cc w/ enclosures: See next page 3 1
l
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Docket File Glainas !
NRC PDR DTondi.
l L PDR JBurdoin !
Docket No.: 50-309_
N/i Rdg RIngram CNel son ELConner
! Yankee Atomic Electric Company r , OELD ATTH: Mr. Robert il. Groco DEisenhut Licensing Engineer 20 Turnpike Road ACRS (16)
Westboro, Itassachusetts 01581 8 h an Gentlemen: IATJCarter Gray File On August 2,1978, representatives from utilities using Combustion Engineering (CE) NSSS and from CE met in Bethesda, Maryland to
! discuss the action requirer.ents in the event of Reactor Protection System (DPS) channel inoperability. Enclosure 1 is the ninutes of this meeting. The meeting was held to clarify our position on this subject as presented in our letter dated October 26, 1977 and to gain an understanding of your position as indicstol in your response dated December 1,1977. This same subject had .co discussed pre-vlously on March 16, 1976.
i In our previous correspondence, we requested that you submit an appli-cation for license anendment to change the Itaine Yankee Technical Specifications (TS) Section 3.9 to require inoperaole RPS channels to be placed in the " tripped" status within one hour after being declared inoperable. Uo further stated that you could request that we under-take a specific facility review of your RPS to determine the suitabil-ity of opcrating the RPS in a two-out-of-three logic. Your response requested such a specific facility RPS review and we propose that the
. flaine Yankee RPS review be'scheduledfor the month of October 1978. j The exact date will be coordinated through your Operating' Reactor Branch !
Project Hanager (ORPil). Enclosure 2 is the RPS review items that will ; )
be of interest to our review team. '
l
\
As-you know, our staff has conducted the RPS review at the Calvert i Clif fs and St. Lucie units. A copy of the resultant Safety Evaluation j for St. Lucie, presenting the finding of the RPS review (pages 3 to 5), j is provided for your information as Enclosure 3. Our conclusion was i j j
-DhIb[Ik 7 l
_______a
k f f Yankee Atomic Electric Co. f that allowing indefinite bypass of one of the four RPS is not justified, but since the four channel CE system does have some independence, bypassing for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during testing or maintenance of one RPS channel is justified.
As an alternative to the onsite NRC review of your RPS, we will consider issuance of the Calvert Cliffs and St. Lucie type TS of your RPS if you provide an application including documentation of your RPS similarity to those of Calvert Cliffs and St. Lucico Any such application should be submitted within 45 days of the date of this letter.
Sincerely, Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors Enlosures:
- 1. Meeting Sumary
- 2. Review Item 5
- 3. Safety Evaluation t
cc w/ enclosures: See next page 4
q;fa- A j T-Mdt.2 e \ n
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!' DISTRIBUTION: l i Docket File Glainas
! NRC PDR DTondi t l'
L PDR JBurdoin Docket No.: 50-285 ORB #4 Rdg RReid RIngram PErickson MConner ,
Ocaha Public Power District Attorney, OELD ATTH: Pr. Theodore E. Short 01&E (3)
Division Hanager - Production DEisenhut Operations TERA, DSB l 1623 Harney Street JRBuchanan Onaha, Nebraska 68102 ACRS - (16)
TCarter Gentlemen: ' Gray File 3 On August 2,1978, representatives from utilities using Combustion Engineering (CE) NSSS and from CE met in Dethesda, Maryland to discuss the action requirements in the event of Reactor Protection System (RPS) channel inoperability. Enclosure 1 is the minutes of this meeting. The meeting was held to clarify our position on this subject as presented in our letter dated December 7,1977 and to gain an understanding of your position as indicated in your response dated January 31, 1978. This same subject had been discussed pre-viously on Itarch 16, 1976, t
j In our previous correspondence, we requested that you submit an appli-f cation for license amendment to change the Ft. Calhoun Technical j Specifications (TS) Section 2.15 to require inoperable RPS channels to
! be placed in the " tripped" status within one hour after being declared l inoperable. We further stated that you could request tnat we under-l take a specific facility review of your RPS to determine the suitabil-
! ity of operating the RPS in a two-out-of-three logic. Your response j requested such a specific facility RPS review and we propose that the j
Ft. Calhoun RPS review be scheduledfor the month of November 1978.
- j. The exact date will be coordinated through your Operating Reactor Branch 4 Project Manager (ORPi-1). Enclosure 2 is the RPS review itens that will be of interest to our review team, ,
l f As you know, our staff has conducted the RPS review at the Calvert '
j Cliffs and St. Lucie units. A copy of the resultant Safety Evaluation for St. Lucie, presenting the finding of the RPS review (pages 3 to 5),
is proviced for your infomation as Enclosure 3. Our conclusion was
' ~
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p a. * ~'
- 4b;f. Q; y.
- .y:y&f!; Q J[ ,3 p 9
?
l Omaha'Public Power District that' allowing indefinite bypass of' one of _ the ~ four_ 'RPSl1s not '
--justified, but since the 'four channel CE system does .have some ,
. independence, bypassing for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during. testing or maintenance l
): of one RPS channel is justifled.
l i l
As.an alternative to the onsite NRC. review of your RPS, we will- !
consider issuance of the Calvert Cliffs and St. Lucie type TS L _ !
. of your RPS:if you provido_ an application including documentation . i of.your RPS similarity to those of Calvert Cliffs-and:St. Lucie. Any .i
'such application ~sh'ould be' submitted within'45' days of the date of l
. this letter. ._
l i Sincerely,- l Jj
.I Robert W. Reid, Chief Operating Roactors Branch #4 Division of Operating Reactors Enlosures:- 1
- 1. . tieeting Summary '
- 2. Review Item l
- 3. Safety Evaluation cc w/ enclosures: See next page j i
t l
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