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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
[Table view] |
See also: IR 05000483/1997005
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UNITE D ST ATES
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.#g %,k NUCLEAR REGULATORY COMMISSION
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REGION IV
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.s 611 RYAN PLAZA DRIVE, Sulf E 400
- 't, ,0[*'- AR LINGTON, T E XAS 760110064
March 3, 1998
Garry L Randolph, Vice President and -
Chief Nuclear Officer
Union Electric Company
P,0, Box 620
FuMon, Missouri 65251
SUBJECT: - RESPONSE TO NRC NOTICE OF VIOLATION (INSPECTION
REPORT 50-483/9745)
Dear Mr. Randolph-
Thank you for your letter of July 25,1997, in response to our June 26,1997, letter and Notice of
Violation concoming the failure to report an event involving a single condition that caused
independent trains to become inoperable and the failure to report plant chances due to
temporary modifications.-
Due to an administrative oversight, this acknowledgment of your response letter was delayed.
We apologize for any inconvenience that this oversight may have caused.
- We have rewswed your reply and find it responsive to the concerns raised in our Notics of
Violation. We will review the implementation of your corrective actions during a future inspection
to determine that full compliance has been achieved and will be maintained.
Sincerely,
)
[
Thomas F. Stetka, Acting Chief
Division of Reactor Safety
Dccket No.: 50-483
License No.: NPF-30
cc:
Professional Nuclear Consu3ing, Inc.
19041 Raines Drive
Derwood, Maryland 20855
0ilO O ?;i ! i
lllR E\E!EE,EMI
9803060277 983303
hDR ADOCK C3000483
PDR
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Union Electric Company -2-
Gerald Chamoff, Esq.
Thomas A. Baxter. Esq.
Shaw, Pittman, Potts & Trowbridge
2300 N. Street, N.W.
Washington, D.C. 20037
H. D. Bono, Supervis ng Engineer
Quality Assurance Regulato;y Support
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 1. Bolef, President
Kay Drey, Representati fe
Board of Directors Coalition
for the Environment
6267 Delmar Boulevard
University City, Missouri 63130
Lee Fritz, Presiding Commissioner
Callaway County Court House
10 East Fifth Street
Fulton, Missouri 65151
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Union Electric Company -3-
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Alan C. Passwater, Manager
Licensing and Fuels
AmorenUE
One Amoren Plaza
1901 Chouteau Avenue
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
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Union Eler*ic Company _ -4-
E-Mail report to T. Frye (TJF)
E-Meil report to T. Hiltz (TGH)
E-Mail report to NRR Event Trocking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK)
bec to DCD (IE01)
boc distrib. by RIV:
Regional Admirktrator Resident inspector
DRS Director DRS Deputy Director
DRP Director _ . DRS-PSB ' ' , _
Branch Chief (DRP/B)- MIS System
Project Engineer (DRP/B) RIV File
Branch Chief (DRP/TSS)
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DOCUMENT NA;AE: R:\CVWCW705ak.tfs
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RIV:AC:EB A
TFStetkallmb (g
03t3/98
OFFICIAL RECORD COPY
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Union F.lectric Company -4-
E-Mail report to T. Frye (TJF) .
E-Mail report to T. Hiltz (TGH)
E-Mail report to NRR Event Tracking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK)
bec to DCD (IE01)
bec distri'o. by RIV:
Regional Administrator Resident inspector
DRS Director DRS Deputy Director .
DRP Director DRS-PSB
Branch Chief (DRP/B) MIS System
Project Engineer (DRP/B) RIV File
Branch Chief (DRP/TSS)
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DOCUMENT N *,ME: R:\CW\CW70Sak.tfs
To recelve copy of document. Indicate in box: "C" = Copy without en osures "E" = Copy w;th enclosures "N" = No copy
RIV:AC:EB ,0 l
TFStetkallmo d&
03/3/98
OFFICIAL RECORD COPY
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Callaway Plant
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futton Misste 65?51 -- ' ~ -
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July 25,1997
U. S. Nuclear Regulatory Commission
Attn: Document Control Desk
Mail Stop Pl-137
Washington, DC 20555-0001 ULNRC-3612
Gentlemen:
REPLY TO NOTICE OF VIOLATION
INSPECTION REPORT NO. 50-483/97005
CALLAWAY PL, ANT
This responds to Mr. Howell's letter dated June 26,1997, which transmitted two Notices
of Violation for events discussed in Inspection Report 50-483/97005. Our response to
these violations is presented in the attachment.
None of the material in the response is considered proprietary by Union Electric.
If you have any questions regarding this response, or if additional infonnation is required,
please let me know.
Very truly yours,
j . V. Laux <h
Manager, Quality Assurance
JVIJtmw/lh
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Attachment: 1) Response to Violations (
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UL,NRC-3612
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July 25,1997
Page 2
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cc: Mr. Ellis W. Merschoff
Regional Administrator
U.S. Nuclear Regulatory Commission ,
Region IV
611 Ryan Plaza Drive, Suite 400
Arlington, TX 76011-8064
Senior Re::ident Inspector
Callaway Resident Office
U.S. Nuclear Regulatory Commission
8201 NRC Road
Steedman,MO 65077
Mr. Barry C. Westreich (2 copies)
Licensing Project Manager, Callaway Plant
Office of Nuclear Reactor Regulation
U. S. Nuclear Regulatory Commission
Mail Stop 13E16
Washington, DC 20555-2738
Manager, Electric Department
Missouri Public Service Commission
PO Box 360
Jefferson City, MO 65102
Mr. Thomas A. Baxter
Shaw, Pittman, Potts, & Trowbridge
2300 N. Street N.W.
Washington,DC 20037
Plan' Manager
Wol. creek Nuclear Operating Corporation
PO Box 411
Burlington,KS 66839
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A. Statement of Violation
During an NRC inspection conducted on February 10-14 and 24-28,1997, two
violations of NRC requirements were identified in accordance with the " General
Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600,
the violations are listed below:
10 CFR 50.73(a)(2)(vii) states, in part, that the licensee shall report any event where
two independent trains or channels become inoperable in a single system designed to
mitigate the consequences of an accident.
Contrary to the above, during Refueling Outage 7, in the spring of 1995, an event
- involving a single condition that caused independent trains to become inoperable
l was not reported. This event involved surveillance tests of the main steam safety
valves that resulted in 14 out of 20 of these valves failing their as-found setpoint
tests with setpoints greater than their Technical Specification setpoint tolerance ofi
I percent.
( This is a Severity Level IV violation (Supplement 1).
Reason for the Violation
Callaway is a four loop plant. Each steam generator is protected from
overpressurization via five safety valves installed or the secondary side steam supply
lines. The lo, vest valve setpoint is 1185 psig. Valve mtpoints are sequenced at
approximately 12 pri increments with a maximum setpoint of 1234 psig to provide
increasing relief capacity based on increasing pressure. This design ensures )
secondary coolant system pressure will be limited to 110% of the design pressure !
during the most severe system operational transient. I
During surveillance testing in Refuel 7, the Main Steam Safety Valves (MSSVs)
were individually tested and set to Technical Specification requirements. One valve
was tested at a time. If a valve failed to meet the Technical Specification criteria, the
action statement was entered, the valve was reset, and the action statement was
exited prior to testing the next valve. At the completion of testing, a summary of the
test results was evaluated for reportability in accordance with Callaway corrective
action program requirements.
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The results were riot considered reportable for the following reasons;
The responae to question 2.3 in NUREO 1022 Revision 0, Supplement I
published February 1984, states that " In general, for the purpose of evaluating
the reportability of situations found during surveillance tests, it should be
assumed that the situation occurred at the time of discovery unless there is
firm evidence to believe otherwise."
Tids position is normally used to determine reportability in accordance with
r 10 CFR 50.73(a)(2)(1)(B) for Technical Specification violaticas. Consistent with the
NUREO position, the failures were considered to occur at the time of discovery since
they were identified during a surveillance test. In addition '.here was no firm
evidence to believe othenvise on individual MSSVs. The action statement was
complied w'th appropriately as each MSSV was tested.
On September 12,1994, an Operating License Amendment, OL #1114, was
submitted to the NRC to increase the Technical Specification setpoint tolerance for
'he MSSVs to +3/ l%. The analysis supporting this amendmem enveloped all but
four of the Refuel 7 as found valve setpoints. Preliminary review of the test data by
Westinghouse (September,1996) determined there was no adverse effect on any
existing safety or fatigue analysis. The operability of the main steam line (i.e., train)
was not adversely impacted by the MSSVs as found condition. The condition noted
did not meet the criteria of 10 CFR 50.72(b)(ii) and 10 CFR 50.73(a)(2)(ii) or
10 CFR 50.72(b)(2)(iii) and 10 CFR 50.73(a)(2)(v) and, therefore, was not
considered to be reportable.
During the subject NRC inspection, the inspectors referred to correspondence from
the NRC Office of Nuclear Reactor Regulation to the Director, Division of Reactor
Safety, USNRC Region IV, dated November 2,1993, in addition to the above
criteria, the letter indicated the most relevant criteria for the case in question was
10 CFR 50.73(a)(2)(vil) which states:
"Any event where a single cause or condition caused at least one independent
train or channel to become inoperable in multiple systems or two independent
trains or channels to become inoperable in a single system designed to :
(A) Shut down the reactor and maintain it in a safe shutdown condition,
(B)Itemove residual heat,
(C) Control the release of radioactive material, or
(D) Mitigate the consequences of an accident"
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The letter refers to guidance contained in the second drah of NUREO 1022,
revision I which indicates that " Valves found outside the technical specification
tolerance band can reasonably be considered to have been inoperable during
operation." The discussion further states "Given that most plants can satisfy
pressure relief requirements with several main steam safety valves unavailable, a
rigid hterpretation of this criterion regarding secondary safety valves (i.e., any case
with more than one safety valve outside the tolerance band) may be overly
Conservative."
Based on review of these criteria the event was not considered to be reportable
because;
1. The cr t ia does not apply at the component level, but at the train level. Steam
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line operability is dependent on operation of the five valves per train as a set.
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The individual valves are not considered to meet the dermition of an independent
train,
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2. The nyaluations discussed above determined that the as found condition of the
valves did not result in their associaied steam lines becoming inoperable.
It should be noted the second draft of NUREO 1022, Rev. I referred to by the NRC
letter, was published for wmment in February 1994, and has yet to be approved for
use. While the information contained in the Region IV letter and the Drah NUREO
may provide useful insights on a particular issue, Union Electric is concemed that
these would be used to develop the basis for a violation, since the review and
approval process is not complete.
On July 14,1997 Westiaghouse supplied an evaluation of the effects ofincreasing
the setpoint tolerance to +3.6% for the MSSVs at Callaway. The evaluation
determined the as found conditions in Refuel 7 would not have impacted system
operability. However, based on the likelihood that a number of the valves exceeded
their acceptance criteria before the time of discovery, and considering all of the out
of tolerance conditions could have existed at the same time, then the condition was
not bounded by the analysis supporting OL #1114. Therefore, this condition should
have been reported as a condition that was outside the design basis of the plant per
10 CFR 50.73(a)(2)(ii).
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The cause of the violation was the failure to adequataly consider all reporting
l requirements and their applicability to the circumstances related to surveillance
testing of MSSVs during Refuel 7.
Corrective Steps Taken and Results Achieved:
A Licensee Event Report will be submitted reporting the as.found condition of the
MSSVs in accordance with 10 CFR 50.73(a)(2)(li).
Corrective Stens to Avold Further Violations:
This event will be reviewed specifically with personnel responsible for making and
approving reportability determinations.
On October 3,1996, OL #1114 was denied by the NRC. Subsequently, Union
Electric contracted with Westinghouse to supply the analysis for a new Operating
License amendment. The Westinghouse analysis will utilize the LOFTRAN code.
The analysis provided with OL #1114 was developed by Union Electric using the
RETRAN code. Use of the LOFTRAN code is expected to expedite the NRC review
process. Union Electric is pursuing a submittal schedule that will support approval
of the Operating License amendment by Refuel 9, targetod for April,1998.
This Operating License amendment will provida Technical Specification acceptance
criteria that are consistent with the operational characteristics of the MSSVs and
current inservice Testing Program performance criteria.
Date when Full Compliance will be Achieved:
Full compliance will be achieved upon approval of the Operating License
amendment.
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11. Statement of Vlotation
During an NRC inspection conducted on February 1014 and 24 28,1997, two
violations of NRC requirements were identified, in accordance with the " General
Statement of Policy and Procedure for NRC Enforcement Actions," NUREO 1600,
the violations are listed below:
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10 CFR 50.59(b)(2) states, in pan, that the licensee shall submit, as specified in
10 CFR 50.4, a report containing a brief descdption of any changes, tests, and
experiments, including a summary of the safety evaluation of each.
Contrary to the above, during the period of June 14,1988, to February 28,1997, a
brief descdption of changes due to temporary modifications (e.g., TM 95-M002) and
the associated safety evaluation summaries were not reported to the NRC.
This is a Severity Level IV violation (Supplement 1).
Reason for the Violation
Procedure APA ZZ-00140, Safety, Environmental and Other Licensing Evaluations
did not require summaries of safety evaluations performed for temporary
modifications to be included in the repon required by 10 CFR 50.59(b)(2).
Temporary modifications had been excluded from this report since they were
typically installed for a limited duration.
Corrective Steps Taken and Results Achieved:
The praunce of not reporting safety evaluation summaries for temporary
modifications began with the reporting period commencing May 1,1987. Letter
ULNRC 1524 dated June 5,1987 represents the last report to include temporary
modification safety evaluation summe. ries prior to the change in reporting criteria.
As a result of thc concem identified during NitC Inspection No. 50 483/97005 safety
evaluation summaries for temporary modifications will be included in future reports.
ULNRC-3580 dated May 9,1997 for the period of May 11,1995 through
December 31,1996 transmitted the most recent summary report as required by
10 CFR 50.59(b)(2) and includes safety evaluation summaries for temporary
modifications for the period.
An ovsluation sas madh 6f tlie reporting periods from May 1,1987 through
May 10,1995 to determine whether any additional actions were warranted. A
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determination was made not to provide summaries of temporary modification nafety
evaluations for this period for the following reasons:
. Temporary modificatloas were short lived and have been removed from the
plant or were incorporated in pennanent design changes which were reported.
- There is no irnpact on the current design and license basis for Callawny Plant.
Corrective Stens to Avoid Further Violation.11
Procedure APA ZZ-00140 guidance for reporting per 10 CFR 50.59(b)(2) has been
corrected to include temporary modification summaries in future reports.
Ibte when Full Compliance will be Achieved:
Full compliance was achieved on June 24,1997
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