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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] |
See also: IR 05000285/1984012
Text
4.
W 2 41985
In Reply Refer To:
Docket: 50-285/84-12
Omaha Public Power District
ATTN: R. L. Andrews, Division Manager-
Nuclear Production
1623 Harney Street
Omaha, Nebraska 68102
Gentlemen:
This refers to your April 9, 1985, response (LIC-85-138) in reply to the
Notice of Violation sent to you with our letter dated March 8, 1985. Our
letter and Notice described a violation which occurred at the Fort Calhoun
Station which was identified during an NRC inspection and investigation
conducted in May, June, and July respectively. The violation was discussed
with you during an Enforcement Conference held with Mr. P. S. Check, Deputy
Regional Administrator, Region IV on December 20, 1984.
Your response has been carefully considered. The response does not contradict
the fact that the violation occurred, and false, inaccurate and incomplete
information was provided to the NRC for review. The information requested,
under oath, by the NRC through the issuance of an IE Bulletin, is considered
material since it was needed to assess the significance of an identified
problem, the potential degradation of threaded fasteners. The key question is
whether the information furnished had a natural tendency or capability to
influence, not whether the information was in fact relied on. In our
opinion, it did have a natural tendency or capability to influence. See
VirginiaElectricPowerCo.(NorthAnna1and2),4NRC480(1976), affirmed
VEPC0 v. NRC, 571 F 2d 1289 (4th. Cir. 1978.). The violation identified by the
~
NRC regardTng your August 2,1982 reply to IE Bulletin 82-02 demonstrated the
need for more effective control of your responses to the NRC. As discussed in
our Notice of Violation, in recognition of prior good performance and prompt and
extensive corrective action, the civil penalty was fully mitigated. However,
since the false statement is considered to be material and is considered to be
more than an inadvertent clerical error as there was a specific lack of emphasis
and attention by several levels of management and supervision within the OPPD
organization, the classification of the violation as a Severity Level III is
appropriate.
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.We find your reply responsive to the-concerns raised in our Notice of
l Violation.- We will review your. corrective action during a. future. inspection
to determine that full compliance has been achieved and will be maintained.-
Sincerely,
.
'
! '
Original signed by
Robert D.' Martin
' Robert D. Martin -
!
. Regional Administrator.
cc:
W. G. Gates, Manager
Fort Calhoun Station
P..O. Box 399
Fort Calhoun, Nebraska 68023
Harry H. Voigt, Esq. ,
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LeBoeuf, Lamb, Leiby & MacRae
f1333 New Hampshire Avenue, NW
Washington, DC 20036
Kansas Radiation Control Program Director
Nebraska Radiation Control Program Director
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Omaha Public Power District
1623 Harney Omaha. Nebraska 68102
402/536 4000
April 9, 1985
LIC-85-138
APRII1985
f4r. James M. Taylcr, Director
Office of Inspection and Enforcement
U. S. Nuclear Regulatory Commission
Washington, DC 20555
Reference: (1) Docket No. 50-285
(2) Letter from OPPD (W. C. Jones) to NRC (J. T. Collins)
dated August 2, 1982 (LIC-82-269)
(3) Letter from OPPD (R. L. Andrews) to NRC (J. T. Collins)
dated July 2, 1984 (LIC-84-209)
(4) Letter from 0 PPD (R. L. Andrews) to NRC (R. D. Martin)
dated December 27, 1984 (LIC-84-434)
(5) Letter from NRC (R. D. Martin) to OPPD (R. L. Andrews)
dated March 8,1985 (EA-84-63)
Dear fir. Taylor:
IE Inspection Report 84-12
Notice of Violation
'
The Omaha Public Power District received IE Inspection Report 84-12 and Reference
(5) both dated March 8, 1985. These documents idertified a potential material
false statement and violation of NRC requirements relative to the District's re-
sponse to NRC IE Bulletin 82-02. Pursuant to 10 CFR 2.201, please find attached
the District's response to these allegations.
Sincerely,
/ Th/sC /
R. L. Andrews
Division Manager
Nuclear Production )
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.1333 New Hampshire Avenue,.N.W.
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Washington, DC 20036
Mr. James R. Miller, Chief ~ .
Office of Nuclear Reactor Regulation
Division of Licensing'
U. S. Nuclear Regulatory Commission-
<
Washington, DC 20555
Mr. Robert D. Martin
Regional Administrator- .
r U. S. Nuclear Regulatory Commission
Region IV
,
611 Ryan Plaza Drive, Suite 1000
Arlington, TX 76011-
Mr. E. G. Tourigny, NRC Project Manager
l .Mr. L. A..Yandell, NRC Senior Resident Inspector
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UNITED STATES OF AMERICA
NUCLEAR REGULATORY COMMISSION
In the Matter of -
Omaha Public Power District ) Docket flo. 50-285
(Fort Calhoun Station, )
Unit No. 1)
'
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AFFIDAVIT
R. L. Andrews, being duly sworn, hereby deposes and says that he is Division
Manager - Nuclear Production of the Omaha Public Power District; that he is
duly authorized to sign and file with the Nuclear Regulatory Commission the
attached response to the flotice of Violation identified in the Commission's
letter dated March 8, 1985 (EA-84-63); that he is familiar with the content
thereof; and that the matters set forth therein are true and correct to the
best of his knowledge, information and belief.
',.b'.?ftie'L
R. L. Andrews
Division llanager
fluclear Production
STATE OF NEBRASKA)
) ss
COUNTY OF DOUGLAS)
Subscribed and sworn to before me, a Notcry Public in and for the State of
Nebraska on this 9 day of April, 1985.
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ATTACHMENT
NOTICE OF VIOLATION
0 PPD Response Pursuant to 10 CFR 2.201
In accordance with Reference 5 and as required therein, the District is
responding to the subject Notice of Violation associated with OPPD's
initial. response to IE Bulletin 82-02 (Reference 2).
VIOLATION
The NOTICE OF VIOLATION attached to Reference 5 states:
The following is a material false statement within the meaning
of Section 186 of the Atomic Energy Act of 1954, as amended.
In the August 2,1982, response to NRC IE Bulletin No. 82-02,
'" Degradation of Threaded Fasteners in Reactor Coolant Pressure
Boundaries in PWR Plants," the licensee stated, in part, that
"The Fort Calhoun Station approved maintenance procedures cal!
'for the use of NEVERSIEZE (sic) (Pure Nickel #65) on all
threaded fasteners."
Contrary to the above statement:
Special Maintenance Procedure SP-RC-11, Revision 1,
" Reactor Coolant Pump Assembly," (effective between
May 24, 1980, and March 1,1983) designated no specific
lubricant on the reactor coolant pump (RCP) studs.
Discussions revealed that it had been common practice to
use molybdenum disulfide lubricant on both.the RCP and
'
reactor vessel studs. Revision 6 of Special Maintenance
Procedure SP-RC-11, dated March 16, 1984, specifically
required the use of " Super-Moly" (molybdenum disulfide)
on RCP Studs.
Maintenance Procedure RC-2-1-B, Revision 12, "S/G Primary
Manway Replacement," (effective between June 9,1981, and
January 20, 1983) designated a mixture of 50% oil and 50%
graphite to be used on manway studs.
The August 2,1982, statement was false in that contrary to the
statement, a number of different types of lubricants were
utilized at Fort Calhoun Station, including " Super-Moly"
(molybdenum disulfide). The false statement was material in
'
that one of the purposes of IE Bulletin No. 82-02 was to find
out which licensees used " Super-Moly" (molybdenum disulfide) as
a fastener lubricant and what plant experience the licensee had
with stress-corrosion cracking of fasteners using molybdenum
,
disulfide lubricants. At the time IE Bulletin 82-02 was
l issued, the NRC thought that molybdenum disulfide might have
,
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VIOLATION'(Continued)
a pronounced tendency to decompose in the presence of high
temperature and moisture conditions to release sulfide, a
known promoter of stress-corrosing cracking. Although the
NRC subsequently found molybdenum disulfide lubricant to be
acceptable, this fact was not known when the licensee sub-
mitted its response.
This. is a Severity Level III violation (Supplement VII).
(No Civil Penalty)
DISTRICT'S RESPONSE
1. Admission or Denial of the Alleged Violation
The District admits that its August 2,1982 response was incomplete,
but den.ies that the alleged violation is a material false statement.
Supplement VII to 10 CFR, Part 2, Appendix C provides that:
A false statement caused by an inadvertent clerical or
similar error involving information which, had it been
available to NRC and accurate at the time the information
should have been submitted, would probably not have
resulted in regulatory action or NRC seeking additional
information
is a " Severity IV violation."
The complete text of that portion of the District's August 2,1982
response that led to the Notice of Violation is as follows:
Request
Identify those closures and connections, if any, where
fastener lubricants and injection sealant materials have
been or are being used and report on plant experience
with their application particularly any instances of SCC
of fasteners. Include types and composition of materials
, used.
!
District's Response
l
Maintenance records indicate that injection sealant
canpounds have never been used on any of the RCPB
enclosures within the scope of IE Bulletin 82-02 at
the Fort Calhoun Station.
The Fort Calhoun Station approved maintenance proce-
dures call for use of NEVERSIEZE Pure Nickel #65 on
all threaded fasteners. To date, the District has ex-
perienced no problems related to use of the NEVERSIEZE
lubricant.
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1. LAdmission or Denial of the Alleged Violation (Continued)
In essence,.the District furdshed three categories of information
to the NRC:
(1) Injection . sealant compounds used,
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(2) Lubricants used on-threaded fasteners, and
(3).
_
Plant' experience with sealants and lubricants, particularly
instances-of stress corrosion cracking of threaded fasteners.
Infomation furnished under Category 1 was accurate; infomation
under Category 2 was incomplete and therefore inaccurate; and
infomation under Category 3 was accurate. The District believes
that its answer in Category 3 must be considered to determine
whether there was any material false statement. The District
accurately reported that it had experienced no problems. That
infomation~was correct with respect to all lubricants used, even
though the lubricants themselves were not al1~1isted. Had the-
other lubricants been identified, no different conclusion con-
cerning their effect would have been presented. Therefore, con-
trary to the Notice of Violation, the statement was not material .
If complete and accurate information had been included in the
District's 1982 response of IE Bulletin 82-02, .it "would probably -
not have resulted in regulatory action or NRC seeking additional
infomation."
Since the NRC acknowledges that the District's incomplete response
was not intentional and was not intended to conceal or mislead, we
also believe it is appropriate to classify it as " inadvertent." In
addition, the Commission has determined that " materiality" should be
contingent upon the safety significance of the. infomation (47 Fed.
Reg. 8584 (1984)). Based upon the above discussion, the District
has-concluded that the inco'nplete response has no safety signifi-
cance.- For all of these reasons, the District submits that its 1982
response was not a material false statement and that classification
as a Severity Level III is not warranted.
2. Reasons for the Violation
Reference 3 described the steps taken to correct the District's
response to Item 5 of IE Bulletin 82-02. Reference 3 also identi-
fied the procedures which were in effect in 1982 when the initial
response was prepared. Further, the inspection conducted by the
NRC's Office of Investigations during June and July of 1984 defines
the causes for the occurrence. The results of the NRC's inspection
are summarized in the third paragraph of Reference 5. The submis-
sion of the statement occurred due to failures on the part of the
District including inadequate review of documentation, failure to
adequately coordinate and discuss the matter with knowledgeable
personnel in the specific area of concern, failure of management
to assign the response to an experienced employee, and failure of
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2. Reason for the Violation (Continued)
management to identify the incomplete statement during the required
procedural review of all the responses to the NRC. The circum-
stances associated with the preparation of the response to the NRC
indicated a specific lack of emphasis and attention to detail by a
number of levels of management and supervision within the District.
3. Corrective Steps Which Have Been Taken and the Results Achieved
As described in the District's presentations to Mr. P. S. Check and
other members of the NRC Region IV staff during the December 20,
1984 Enforcement Conference, corrective measures have been taken in
three-areas:
(1) Review of the qualifications of those responsible for
preparing NRC response for the years 1983 and 1984.
(2) Re' vision of the trainirg program for new technical
employees.
(3) Establishment of internal procedures for checking sub-
mittals to the NRC and independently reviewing submittals
requiring oath or affimation and as otherwise deemed
appropriate prior to management review. '
These measures and the results achieved are summarized below.
(1) . Review of Preparer's Qualifications
An undocumented review and evaluation of correspondence
submitted under oath or affirmation for the last two years
(1983-1984) was conducted to address the following functions:
a. Were the individuals who prepared responses experienced
in the area of the response?
b. Is it necessary to perfom a technical review of any
responses submitted during 1983 and 1984?
c. Is it necessary to conduct a review and evaluation of
correspondence submitted prior to 1983?
The results of that review and evaluation are as follows:
Items submitted under oath or affirmation fit into three
general categories:
- Technical Specification Amendment Applications (both
initial applications and revisions to previously filed
applications)
.
,
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Proprietary Information Declarations
- IE Bulletin and Generic Letter Responses
-4-
. _ _ _ _ _ _ _ _ _ _
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3. Corrective Steps Which Have Been Taken and the Results Achieved
,
(Continued)
Technical Specification Amendment Application
The review and evaluation concluded that since Technical
Specification Amendments were reviewed and approved by the
Plant Review Committee and the Safety Audit and Review
Committee, the detailed reviews and approvals of these two
groups was sufficient to ensure that the information was
correct. In addition, the Commission approved such appli-
cations in the form of Amendments to the District's Technical
Specifications. Based on the above, the District believes
that no additional review is necessary for the Technical
Specification Amendments submitted during 1983-1984. The
review and evaluation also concluded that it is highly un-
likely that a similar situation to the IE Bulletin 82-02
response could occur with Technical Specification Amendment
applications. It was also detemined that it was not neces-
sary to do additional reviews on the Technical Specification
Amendments submitted prior to 1983 since they were handled
in a similar manner as the 1983-1934 applications.
,
Proprietary Information Declarations
The review and evaluation concluded that Proprietary Infor-
mation Declarations are not nomally of a type where safety
significant information is provided to the Commission.
Therefore, no additional review of Proprietary Infomation
Declarations submitted during 1983-1984 was needed nor was
it necessary to review such submittals prior to 1983. The
review and evaluation also concluded that it is highly un-
likely that a similar situation to the IEB 82-02 response
could occur with Proprietary Information Declarations.
-
IE Bulletin and Generic Letter Responses
The review and evaluation concluded that the personnel who
initially prepared IE Bulletin and Generic Letter responses
submitted under oath or affirmation during 1983-1984 were
sufficiently experienced to prepare such responses. These
IE Bulletins and Generic Letter responses were processed
through the District's management review cycle. As described
in Item (3) on Page 7 of this response, the District procedure
for processing of f1RC and other regulatory correspondence
(DAS-L-03) was revised in September 1984 to incorporate an
independent review and checking function. Since that revi-
sion, IE Bulletins and Generic Letters submitted under oath
of affimation have been independently reviewed as required.
For 1983 and 1984 IE Bulletins and Generic Letter responses
that were submitted prior to September 24, 1984, the following
action was taken.
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3. Corrective Steps Which Have Been Taken and the Results Achieved
(Continued) g
a. Many of the personnel responsible for preparing i
these responses have been interviewed in order to 4
determine if additional review is required. During -
these interviews, personnel were asked to describe
the steps they used in preparing the response with
the intention of determining whether the necessary
steps were taken. Based on these interviews it was
determined that the necessary steps were taken; -
consequently, no additional review was required.
b. Some responses were discussed at several meetings
where sufficient qualified personnel were present %
and extensively discussed the subject matter. The -:
responses were then prepared ba;ed on those discus- _
sions and the documents were subsequently processed *
through the District's correspondence review cycle.
c. Some of the IE Bulletins or Generic Letter re- Y
sponses have subsequently been reviewed by the J
Commission and closed.
Based on the above information it has been concluded that it 7
is not necessary to conduct further reviews of the IE Bulletin 5
'"
and Generic Letter responses submitted for the 1983-1984
period or made before 1983. g
_
this review provides confidence that it is unlikely that a 3
similar situation to the IEB 82-02 response could occur with I
the IE Bulletin and Generic Letter responses submitted before 2
or during the 1983-1984 period. j
'=
The District cannot positively state that all responses '
submitted to the Commission are 100'. complete and accurate; 7
however, the District can state there is a high degree of -
assurance that responses submitted to the Commission are =
complete and accurate based on past reviews and the results 7
of the review and evaluation which was conducted prior to i
the December 20, 1984, Enforcement Conference.
(2) Revision of the Training Program for New Technical Employees
Training of new tehnical employees has been upgraded by the i
availability of additional courses in reactor and power plant a
fundamentals. Further, availability of training materials and y
resources has been formalized and implemented by the Nuclear l
Production Division (NPD) as described in the NPD Policy / i
Procedure No. C-3, R0 2/15/85, " Orientation / Training of Newly ?
Hired Technical Employees Performing Safety-Related Activi- e
ti es . " Policy / Procedure C-3 training of managers and super- 3
visors in NPD and managers in the Engineering Division was
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3. Corrective Steps Which Have Been Taken and the Results Achieved 1
(Conti nued) 7
.
completed on February 12, 1985. New technical employees in j
the Nuclear Production Division will be trained under this a
upgraded training and orientation policy. These improve- $
ments improve employee awareness of existing documentation, y
resources, and 'nfonnation prior to preparation of responses. ]
Also, utilization of this policy encourages communication
between the supervisor and new employee to provide the
supervisor with a thorough understanding of the employee's 4
capabilities. 4
-)
The improvement of the training program and formal establish- 4
ment of an NPD training policy for new employees has resulted -d
in increased managerial and supervisory awareness that indivi- 2
duals preparing responses must be properly qualified prior to ;
being assigned as a preparer. Similar policies are in effect g
in the Engineering Division. I
Al
Establishment of Internal Procedures for Checking and
--
(3) -
Independently Reviewing Submittals to the NRC.
The District's Nuclear Regulatory & Industry Affairs depart- 7
mental procedure for processing of NRC and other regulatory m
correspondence (DAS-L-03) was revised in September 1984 to a
incorporate appropriate Independent Review requirements as ?
well as Checks of responses. In accordance with the proce- i
dure as revised, NRC submittals now undergo a Check which is j
generally an intradepartmental review of the originating NRC 3
document against the submittal to confinn that items are -
adequately addressed, properly stated and the responses are _
complete. A Check is normally done by a knowledgeable person i
or the preparer's supervisor or manager. Q
Correspondence from the NRC is reviewed upon receipt to deter- I
mine if a response is required and if that response should be =
independently reviewed. Review of such responses are assigned ;
to an OPPD organization separate from the initial preparer's -
for an Independent Review, which is generally an interdepart- s
"
mental review of the NRC originating document against the
submittal to confinn that all items are adequately addressed, 3
properly stated and the responses are complete and technically 4
correct. The Independent Reviewer confirms that information 5
in the submittal is accurate and correct. Also, the Indepen- '
dent Reviewer confirms that the supporting data in the sub-
mittal supports the submitted conclusion. j?
Either a Check or the Independent Review are completed prior 3
to management review of the proposed NRC response. These i
Checks assure that the preparer and the preparer's super- 5
visor have reviewed apprcpriate documentation and available j
resources so that responses are complete and accurate in ,
4
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3. Corrective Steps Which Have Been Taken and the Results Achieved
(Continued)
detail. Independent Reviews add these same features plus
the review of a knowledgeable third party.
The District's experience since revision of DAS-L-03 has
indicated that Independent Reviews and Checks are providing
a thorough review of the responses, thereby reducing the
likelihood of further similar violations.
4. The Corrective Steps Which Will Be Taken to Avoid Further Violations
Experience'with the process of Independent Reviews and Checks of
responses indicates that additional corrective steps are not neces-
sary; however, the training programs for new and seasoned employees
are anticipated to improve as further training resources become
available and supervisors become better acquainted with application
of these training resources to their employees' training and re-
training needs.
5. The Date When Full Compliance Will Be Achieved
The District is currently in full compliance.
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