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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K1051999-10-19019 October 1999 Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML20217B5901999-10-0505 October 1999 Informs That Staff Concludes That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Callaway Plant,Unit 1 ML20217B5711999-10-0505 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & Uec Responses for Callaway NPP Unit 1 ,990224 & 990628.Informs That Staff Reviewed Responses & Concluded That All Requested Info for GL 98-01 Provided ML20212G0221999-09-22022 September 1999 Forwards Insp Rept 50-483/99-11 on 990812-20.No Violations Noted.Team Found,Weakness in flow-accelerated Corrosion Monitoring Program Resulted in No Previous Insp of Pipe Segment Which Failed ML20212D9341999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Callaway Plant.In Area of Ep,C/As Taken in Response to Problems Identified During Previous Exercises Warrant More in-dept Review.Details of Insp Plan Through March 2000 Encl ML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4921999-09-13013 September 1999 Forwards Insp Rept 50-483/99-08 on 990725-0904.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20212B1521999-09-10010 September 1999 Forwards Insp Rept 50-483/99-07 on 990809-13.No Violations Noted.Inspectors Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML20211N0321999-09-0202 September 1999 Forwards SE Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20211B0241999-08-18018 August 1999 Ack Receipt of Ltr Dtd 990714,transmitting Scenario for Licensee Upcoming Biennial Exercise.Based on Review,Nrc Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20210T9121999-08-13013 August 1999 Forwards Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) 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 ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ML20210P0371999-08-10010 August 1999 Forwards SE Granting Licensee 980710 Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code for Second 10-year Interval ISI at Plant,Unit 1 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 ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210H6381999-07-30030 July 1999 Forwards SE Accepting Relief Request for Approval for Use of Alternate Exam Requirement for Plant Inservice Insp Program A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20210B5611999-07-20020 July 1999 Forwards Review of Ltr & Encl Objectives for Plant,Unit 1,1999 Emergency Plan Exercise Scheduled for 990914 ML20210B4021999-07-19019 July 1999 Ack Receipt of Facility Emergency Plan Implementing Procedure EIP-ZZ-00101, Classification of Emergencies, Rev 23,issued on 990513,under Provisions of 10CFR50,App E, Section V ML20210B4401999-07-19019 July 1999 Ack Receipt of Revs to Facility Radiological Emergency Response Plan,Chapters 8.0 & 4.0,issued Respectively on 990512-14,under Provisions of 10CFR50,App E,Section V ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209E5591999-07-0808 July 1999 Informs That as Result of NRC Review of Util 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.TAC MA0531 Closed ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20196J9501999-07-0202 July 1999 Ack Receipt of Plant Ep,Rev 22,received on 981207 & Submitted Under Provision of 10CFR50,App E,Section V.Changes Does Not Decrease Effectiveness of EP & Continues to Meet Stds of 10CFR50.47(b).NRC Approval Not Required ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20196F8101999-06-25025 June 1999 Informs That J Donohew Will Assume Project Manager Responsibilities,Effective 990621 ML20196H2521999-06-25025 June 1999 Forwards Insp Rept 50-483/99-05 on 990502-0612.Two Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20196F8181999-06-24024 June 1999 Forwards RAI Re 990111 Request for Relief from Certain ASME Code ISI Requirements for Containment Liners.Response Requested within 30 Days from Date of Agreement ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve IR 05000483/19990041999-06-18018 June 1999 Refers to GL 96-05 Issued by NRC on 960918,UE Responses & 970313 & NRC Insp Rept 50-483/99-04,dtd 990427. Forwards Request for Addl Info Re GL 96-05 Program at Callaway Plant,Unit 1 ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H0971999-06-14014 June 1999 Discusses Une 990407 Request That Proprietary Document Entitled, Thermal Stability Assessment - Electrosleeved Tubes, Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20207H3751999-06-14014 June 1999 Discusses 990407 Une Request That Proprietary Version of Document Entitled, Evaluation of Severe Accident Simulation, Dtd April 1999,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20207G3201999-06-0707 June 1999 Ack Receipt of Change Notice 98-008 Dtd 980918,which Transmitted Changes to Callaway Plant Ep,Rev 21,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required.No Violations Identified ML20207G3151999-06-0707 June 1999 Ack Receipt of Callaway Plant EP Implementing Procedure EIP-ZZ-001001M,Classification of Emergencies,Rev 22,issued on 981222 Under 10CFR50,App E,Section V Provisions.No Violations Identified ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS 1999-09-22
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217K1051999-10-19019 October 1999 Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML20217B5901999-10-0505 October 1999 Informs That Staff Concludes That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Callaway Plant,Unit 1 ML20217B5711999-10-0505 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & Uec Responses for Callaway NPP Unit 1 ,990224 & 990628.Informs That Staff Reviewed Responses & Concluded That All Requested Info for GL 98-01 Provided ML20212G0221999-09-22022 September 1999 Forwards Insp Rept 50-483/99-11 on 990812-20.No Violations Noted.Team Found,Weakness in flow-accelerated Corrosion Monitoring Program Resulted in No Previous Insp of Pipe Segment Which Failed ML20212D9341999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Callaway Plant.In Area of Ep,C/As Taken in Response to Problems Identified During Previous Exercises Warrant More in-dept Review.Details of Insp Plan Through March 2000 Encl ML20212A4921999-09-13013 September 1999 Forwards Insp Rept 50-483/99-08 on 990725-0904.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212B1521999-09-10010 September 1999 Forwards Insp Rept 50-483/99-07 on 990809-13.No Violations Noted.Inspectors Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML20211N0321999-09-0202 September 1999 Forwards SE Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20211B0241999-08-18018 August 1999 Ack Receipt of Ltr Dtd 990714,transmitting Scenario for Licensee Upcoming Biennial Exercise.Based on Review,Nrc Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20210T9121999-08-13013 August 1999 Forwards Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy 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 ML20210P0371999-08-10010 August 1999 Forwards SE Granting Licensee 980710 Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code for Second 10-year Interval ISI at Plant,Unit 1 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 ML20210H6381999-07-30030 July 1999 Forwards SE Accepting Relief Request for Approval for Use of Alternate Exam Requirement for Plant Inservice Insp Program ML20210B5611999-07-20020 July 1999 Forwards Review of Ltr & Encl Objectives for Plant,Unit 1,1999 Emergency Plan Exercise Scheduled for 990914 ML20210B4401999-07-19019 July 1999 Ack Receipt of Revs to Facility Radiological Emergency Response Plan,Chapters 8.0 & 4.0,issued Respectively on 990512-14,under Provisions of 10CFR50,App E,Section V ML20210B4021999-07-19019 July 1999 Ack Receipt of Facility Emergency Plan Implementing Procedure EIP-ZZ-00101, Classification of Emergencies, Rev 23,issued on 990513,under Provisions of 10CFR50,App E, Section V ML20209E5591999-07-0808 July 1999 Informs That as Result of NRC Review of Util 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.TAC MA0531 Closed ML20196J9501999-07-0202 July 1999 Ack Receipt of Plant Ep,Rev 22,received on 981207 & Submitted Under Provision of 10CFR50,App E,Section V.Changes Does Not Decrease Effectiveness of EP & Continues to Meet Stds of 10CFR50.47(b).NRC Approval Not Required ML20196F8101999-06-25025 June 1999 Informs That J Donohew Will Assume Project Manager Responsibilities,Effective 990621 ML20196H2521999-06-25025 June 1999 Forwards Insp Rept 50-483/99-05 on 990502-0612.Two Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20196F8181999-06-24024 June 1999 Forwards RAI Re 990111 Request for Relief from Certain ASME Code ISI Requirements for Containment Liners.Response Requested within 30 Days from Date of Agreement IR 05000483/19990041999-06-18018 June 1999 Refers to GL 96-05 Issued by NRC on 960918,UE Responses & 970313 & NRC Insp Rept 50-483/99-04,dtd 990427. Forwards Request for Addl Info Re GL 96-05 Program at Callaway Plant,Unit 1 ML20207H3751999-06-14014 June 1999 Discusses 990407 Une Request That Proprietary Version of Document Entitled, Evaluation of Severe Accident Simulation, Dtd April 1999,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20195H0971999-06-14014 June 1999 Discusses Une 990407 Request That Proprietary Document Entitled, Thermal Stability Assessment - Electrosleeved Tubes, Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20207G3151999-06-0707 June 1999 Ack Receipt of Callaway Plant EP Implementing Procedure EIP-ZZ-001001M,Classification of Emergencies,Rev 22,issued on 981222 Under 10CFR50,App E,Section V Provisions.No Violations Identified ML20207G3201999-06-0707 June 1999 Ack Receipt of Change Notice 98-008 Dtd 980918,which Transmitted Changes to Callaway Plant Ep,Rev 21,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required.No Violations Identified ML20207E2711999-05-25025 May 1999 Ack Receipt of in Response to & Insp Rept Confirming Commitment as Stated by M Taylor During Telephonic Exit Meeting on 990413 ML20207A8711999-05-24024 May 1999 Informs That NRR Reorganized,Effective 990328.Forwards Organization Chart ML20207A4131999-05-19019 May 1999 Forwards Insp Rept 50-483/99-03 on 990321-0501.One Violation of NRC Requirements Identified & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20206K6511999-05-10010 May 1999 Forwards RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206N3981999-05-10010 May 1999 Responds to Comments & Questions Submitted to NRC Staff Re Recent License Amend Issued by NRC to Callaway Unit 1 License.Provides Context for Conclusion That Reracking of Callaway SFP Maintains Adequate Protection of Public Safety ML20206H1101999-05-0606 May 1999 Forwards Results of Gfes of Written Operator Licensing Exam, Administered on 990407,to Nominated Employees of Facility. Requests That Training Dept Forward Individual Answer Sheets & Results to Appropriate Individuals.Without Encl ML20206H1821999-05-0606 May 1999 Forwards RAI Re Licensee Request for Relief from Certain ASME Code ISI Requirements Submitted by .Response Requested within 30 Days of Receipt of Ltr ML20206F4931999-05-0303 May 1999 Forwards Exam Rept 50-483/99-302 on 990416.Insp Included Evaluation of Applicant for Reactor Operator License ML20205S2571999-04-19019 April 1999 Discusses Plans to Sponsor Testing of Electrosleeved Tubes to Better Understand Behavior of Electrosleeve Matl Under Severe Accident Conditions ML20205Q5461999-04-19019 April 1999 Forwards Safety Evaluation Relief Request from Certain ASME Section XI Requirements for Concrete Containment ISI for Plant ISI Program ML20205K7641999-04-0808 April 1999 Ack Receipt of Re Comments & Questions Concerning Recent Amend to Plant,Unit 1.Response to Comments & Questions Should Be Completed by mid-May ML20205J8701999-04-0606 April 1999 Ack Receipt of ,In Response to NRC Insp Rept 50-483/99-02,dtd 990225 Re Verbal Commitment Made During Exit Meeting for Insp.Understands Next Rev of Security Plan Will Include Increased Min Staffing of Three Armed Guards ML20205J8721999-04-0505 April 1999 Refers to Meeting Conducted in Emergency Operations Facility at Callaway Plant on 990401 Re Plant Performance Review for Plant Completed on 990211.Year 2000 Readiness Issues & New Reactor Licensee Performance Assessment Also Discussed ML20205J9401999-04-0505 April 1999 Forwards Insp Rept 50-483/99-01 on 990207-0330.One Violation Occurred & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy IR 05000019/20250011999-04-0202 April 1999 Informs That Version of Topical Rept BAW-10219P,Rev 3 Dtd Oct 1998 & Document 51-5001925-01,dtd 980828 Will Be Marked as Proprietary & Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act ML20205A3821999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Callaway Plant Performance Review for Period 970510-990125. Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl ML20204E7281999-03-18018 March 1999 Ack Receipt of Which Transmitted Rev 28 to Callaway Plant Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Util Determined Changes Do Not Decrease Effectiveness of Plan ML20204E3671999-03-18018 March 1999 Informs That During 990128 Telcon Between D Lantz & H Bundy, Arrangements Were Made for Administration of Retake Written Operator Licensing Exam at Plant,During Wk of 990419 ML20204B7091999-03-15015 March 1999 Informs That Changes Described in ,Submitting Rev 20 to Plant Operational QA Manual,Appear Consistent with Guidelines for non-reduction in Committments ML20204C4241999-03-15015 March 1999 Forwards Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20207F4731999-03-0404 March 1999 Discusses 990302 Public Meeting Re Program Updates & Organizational Changes in Emergency Preparedness & Security. List of Attendees & Licensee Presentation Encl ML20207L6491999-03-0404 March 1999 Informs That Util 990111 Response to Request for Addl Info Re Question 4 Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.709(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended 1999-09-22
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EA 97-168 Garry L Randolph,-Vic6 President and Chief Nuclear Officer Union Electric Company :
-P.O. Box 620 Fulton, Missouri 65251 SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORT 50 483/97 05)
Dear Mr. Randolph:
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This is in reference to the predecisional enforcement conference conducted with you and
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other Union Electric Company representatives on August 15,1997, in the NRC's Arlington, Texas office, and subsequent requests for additional information, as discussed below. The conference was conducted to discuss three apparent violations of NRC requirements related to the Callaway Plant. The apparent violations were identified during an NRC inspection completed on June 24,1997, and were described in an inspection report issued June 26,1997,. Following receipt of the inspection report, which indicated that the NRC
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was considering escalated enforcement action for these apparent /iolations, Union Electric requested a predecisional enforcement conference.
The apparent violations involved three instancer in which it appeared that safety evaluations required by 10 CFR 50.59 had not been performed for changes to the facility as it is described in the Final Safety Analysis Report, including: 1) a Technical Specification interpretation (TSI) and related procedures that permitted manual operation of
' diesel generator bui' ding supply fans: 2) a TSI that modified overload and load reduction trip setpoints for the refueling machine; and 3) a modification that required manual operation of the Post Accident Sampling System (PASS). With respect to manual l
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operation of diesel generator building supply f ans, the NRC's concerns included whether /
this change resulted in an unreviewed safety question (USQ), which would have required
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NRC approval prior to the change, and whether emergency diesel generator technical .
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f specifications may have been violated when the diesel generator building supply fans were in the . manual ti.e., pull-to lock)-mode of operation. .
At the conference, Union Electric: acknowledged that the diesel generator building supply fan issue had not been subjected to a safety evaluation from 1985 to 1987; characterized
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the PASS issue as an isolated f ailure to implement 10 CFR 50.59; and denied any violation related to the refueling machine issue. Union Electric also stated that: 1) none of the changes involved USQs; 2) no technical specification violations had occurred; and 3) there
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twas no safety significance to any of the issues. Following the conference, the NRC-
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requested additional technicalinformation from Union Electric regarding its position that the 9710290172 971022
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Union Electne Company 2-operability of the emergency diesel generators would not be affected with the building supply f ans in the " pull to-lock" mode. Union Electric provided additional information in letters dated Septernber 15 and October 2,1997.
Based on the information developed during the inspection and our review of the information that you provided during and subsequent to the conference, the NRC has determined that violations of NRC requirements occurred in each instance discussed above.
The violations are cited in the enclosed Notice of Violation (Notice); the circumstances surrounding the violations were described in the subject inspection report, Although the NRC believes in each case that safety evaluations were not performed as required by 10 CFR 50.59, we view these as isolated failures to assure consistency with the FSAR and not indicative of a programmatic concern. In addition, there were no actual safety consequences as a result of any of these changes. Therefore, each of the violations has been classified at Severity LevelIV in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy), NUREG-1600.
Nonetheless, it is important for Union Electric to understand that changes to the f ac"ity or to procedures described in the FSAR that are not subjected to safety evaluations may result in unrecognized USOs. Until such changes are subjected to safety evaluations and are well understood, there is uncertainty in the basis (the FSAR) upon which the NRC made a decision to license the facility. Thus, if changes are made that result in unrecognized USQs, the NRC would consider the failure to follow the regulatory process established by 10 CFR 50.59 as a significant regulatory concern.
With regard to the diesel generator building supply f ans (Violation A), described in the FSAR as automatically starting when room temperatures exceed 90 F and shutting down automatically when room temperatures fall below 86 F, Union Electric's position at the conference was that a safety evaluation had been performed in late 1986 which showed that the supply fans were not needed as long as outside air temperatures were below 65*F. This analysis resulted in TSI No. 35 in February 1987 which allowed diesel generators to be considered operable with the supply fans out of service and outside temperatures less than 65 F. Union Electric's position, therefore, was that from February 1987 forward, sufficient guidance existed to operators to preclude placing the f ans in pull-to lock if outside temperatures were above 65 F. Union Electric also stated that a recent analysis showed that operability of the diesel generators would not be affected even if supply fans were inoperable and outside temperatures were at 97aF, the maximum outside temperature assumed in the FSAR.
Notwithstanding Union Electric's position on this issue, the f act remains that at the time of the NRC's on site inspection in February 1997, TSI No.18 and Procedure OTN NE-0002 (and superceded procedures OTN NE-0001 A and OTN-NE-0001B) permitted placing the supply f ans in pull to-lock "... provided it is still under the total control of the Reactor Operator." The TSI and procedure indicated that this was based on hdministrative controls that allow the operator to maintain the room temperature below the FSAR (and former
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Technical Specification) !imit of 119 F. This provision, which appears to have permitted
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_ Union Electric Company -3-placing the fans in pull to lock regardless of outside temperatures, was inconsistent with the FSAR and was not subjected to a safety evaluation, as required by 10 CFR 50.59, Union Electric's position on the refueling machine issue (Violation B)is that the trip setpoints were in accordance with applicable vendor guidance and interpretations, and, therefore, that there was no change to the description in the FSAR._ This position is based on an interpretation _that the trip setpoints were aporopriately set based on the heaviest and lightest loads, and not on the " suspended loads" as indicated in Section 16.9.2.1 of the FSAR The NRC disagrees with this interpretation because the FSAR descripti_on of these trip setpoints indicates an expectation that the actual or estimated weight of the ,
suspended load is considered in setting the trip points by referring to the overload trip l setpoint in relation to the "... indicated suspended weight." Therefore, we conclude that TSI No. 25 was inconsistent with the description in the FSAR and that this change had not been subjected to a safety evaluation.
With regard to the PASS issue (Violation C), Union Electric agreed that a modification to the PASP was made which altered the operation of the system from that described in the FSAR, ard that elimination of computer-controlled operation of the system had not specifically been subjected to a safety evaluation. Union Electric attributed this to a mistalren belief, when the actual modification was made, that all changes from the FSAR had previously been analyzed.
As previously stated, the NRC does not view these violations as an indication of a programmatic concern with respect to the implementation of 10 CFR 50.59 at the Callaway Plant. But there are lessons to be learned, nonetheless. For example, as discussed at the conference, an FSAR description that requires a carefully worded interpretation, as in the case of the refueling machine trip setpoints, should be revised.
_
With regard to the diesel generator building supply f an TSI, the guidance that was provided to operators was confusing, at best, and seemed to serve little purpose after 1990 when the hardware problem that was the genesis for TSI No.18 was fixed. The NRC supports Union Electric's stated plan to eliminate as many TSis as possible.
You are required to respond to this letter and should follow the instructions specifiad in the enclosed Notice when preparing your response. The NRC will use your response, in part, to determine whether further enforcement action is necessary to ensure compliance with regulatory requirements, in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its enclosure, and your response will be placed in the NRC Public Document Room.
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Sincerely, i
Ellis W. Merse Regional Administrator
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_.
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Union Electric Company 4-Docket: 50-483 License: NPF-30 Enclosure: Notice of Violation cc w/ Enclosure:
.,
Professional Nuclear Consulting, Inc.
.19041 Raines Drive Derwood, Maryland 20855 Gerald Charnoff, Esq.
Thomas A. Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.
Washington,-D.C. 20037 H. D. Bono, Supervising Engineer Site Licensing Union Electric Company P.O. Box 620 Fulton, Missouri 65251 Manager - Electric Department Missouri Public Service Commission 301 W. High P.O. Box 360 Jefferson City, Missouri 65102 Ronald A. Kucera, Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, Missouri 65102 Otto L. Maynard, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66839 ,
Dan I. Bolef, President Kay Drey, Representative i Board of Directors Coalition for the Environment 6267 Delmar Boulevard University City, Missouri 63130 l
I l
. .
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Union Electric Company -5-Lee Fritz, Presiding Commissioner-Callaway County' Court House
- - 10 East Fifth Street Fulton, Missouri 65151 Alan C. Passwater, Manager Licensing and Fuels Union Electric Company -
P.O. Box 66149 St. Louis, Missouri 63166 6149
- J.'V. Laux, Manager Quality Assurance Union Electric Company P.O. Box 620 Fulton, Missouri 65251 f'
- -
Union Electric Company -6-bec w/ Enclosure: [
I rt 4 PDR LPDR 4UDOCS SECY EC's: RI, Ril, Rlli CA PA (0 2G4)
EDO (017G21) OlG (T-5D28)
DEDO (017G21) OE (0-7H5)
OE:EAFile (0-7H5) 01 (0 3E4)
OGC (015B18) OGC (0-15818)
NRR (0-12G18) NRR/ADP (0-12G18)
OC/DAF (T-9E10) OC/LFDCB (T-9E10)
AEOD (T-4D18)
RA R3ading File GSanborn-EAFile RIV Files MIS Coordinator PAO RSLO RIV Files TStetka E-Mall DISTRIBUTIQN:
OEMAIL JDyer (JED2)
EMerschoff (EWM) WBrown (WLB)
GSanborn (GFS) GMVasquez (GMV)
AHowell (ATH) DChamberlain (DDC)
WJohnson (WDJ) TStetka (TFS)
PGwynn (TPG) KBrockman (KEB)
DPasschl (DXP) WBateman (WHB)
KThomas (KMT)
DOCUMENT NAME: G:\EA\ DRAFT \EA97168.DFT To receive copy of document, indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "t** = No copy EO C:EB D:DRS RC b(iA
'SANBORN ' STETK A ' AHOWELL "WBROWN JDYQR 10/17/97 10/20/97 10/20/97 10/21/97 10/ /B7 h RR/PD4-h n\@RA~ '{g { l l l l BATEMAN%'g MER9dROFF 10fA97 ggcq 10 ( )97 '
- previously cdh6urred D~FFICIAL RECORD COPY
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e Union Electric Lompany -6-bec w/ Enclosure:
PDR IE 14 LPDR NUDOCS SECY EC's: Rl,Ril,Alli CA PA (0 2G4)
EDO (017G21) OlG (T-5D28)
DEDO (017G21) OE (0-7H5)
OE:EAFile (0-7H5) 01 (0-3E4)
l OGC (0-15B18) OGC (015B18)
NRR (012G18) NRR/ADP (012G18)
OC/DAF (T 9E10) OC/LFDCB (T 9E10)
AEOD (T-4D18)
RA Reading File GSanborn-EAFile RIV Files MIS Coordinator PAO RSLO RIV Files TStetka E Mall DISTRIBUTION:
OEMAll JDyer (JED2)
EMerschoff (EWM) WBrown (WLB)
GSanborn (GFS) GMVasquez (GMV)
AHowell (ATH) DChamberlain (DDC)
WJohnson (WDJ) TStetka (TFS)
PGwynn (TPG) KBrockman (KEB)
DPassehl (DXP) WBateman (WHB)
KThomas (KMT)
DOCUMENT NAME: G:\EA\ DRAFT \EA97168.DFT To receive copy of pcument, inscete in box: ac = copy weout fnclosures *E" = Copy we enposures "N" = No copy EO ff/\, C:EB , D:DRS M RC /R% DRA SANBO W1G STETKAq% ,_ AHOW ELV WBROWNV JDYER 10ff/97 10/po/9749910GQ97 10/p/97 10/ /97 RA l MERSCHOFF __
10/ /97
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OFFiClAL RECDRD COPY