Letter Sequence Other |
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Results
Other: 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant, 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420, A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage, BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001, ML20147F998, ML20147G854, ML20148A890, ML20148B666, ML20148K225, ML20148Q724, ML20149M198, ML20150A899, ML20150B182, ML20150B526, ML20150C407, ML20150D397, ML20151A945, ML20151B202, ML20151E018, ML20151E419, ML20151E868, ML20151G115, ML20151G791, ML20151H779, ML20151H965, ML20151Q920, ML20154D233, ML20154E154, ML20155A456, ML20155E392, ML20196H353, ML20205P688, ML20235J165, ML20235J168, ML20236A614, ML20236A849, ML20236D105, ML20236F547, ML20236S018, ML20247K075, NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers, RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant, W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin
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MONTHYEARML20235S2971987-10-0202 October 1987
Summary of 870923 Meeting W/Westinghouse Re Technical Basis for Westinghouse Recommended Actions,Criteria & Conclusions in to Utils That Use Models DS-416,DSL-416, DS-420,DS-206 & DSL-206 Switchgear in Class 1E Svc
Project stage: Meeting
ML20236A6141987-10-16016 October 1987
Advises That Util Insp of Reactor Trip Breakers Revealed Catawba Pole Shaft Which Had Welds W/Indications of Cracking.Forwards Informal Technical Communication from Franklin Research Ctr Re Initial Observation
Project stage: Other
ML20236A8491987-10-16016 October 1987
Forwards I.6177-5-1, Interim Rept on McGuire Reactor Trip Breaker 2B Failure Evaluation & Rcommended Corrective Actions from Westingtonhouse. Rept Explains Mechanical Binding Which Kept Breaker from Opening on 870702
Project stage: Other
ML20236D1051987-10-21021 October 1987
Provides Record of 871020 Telcon Between D Hood,D Sellers & V Hodge of NRC & J Mcvicker & Cowne of Bg&E Re Unit 1 480 Volt Circuit Breaker W/Broken Weldment Connecting Ctr Pole Lever to Pole Shaft.Util Exam Results in 860918 Memo
Project stage: Other
ML20236F5471987-10-23023 October 1987
Documents 871020 Telcon W/Util Re Unit 2 Circuit Breaker Pole Shaft Weld Failure
Project stage: Other
ML20236F9651987-10-27027 October 1987
Notification of 871103 Meeting W/Util & Westinghouse in Philadelphia,Pa to Discuss Results of Franklin Research Ctr Exam of Cracks in Pole Shaft Welds of Reactor Trip Breaker
Project stage: Meeting
ML20236S0181987-11-18018 November 1987
Summarizes 871020 Telcon Between NRC & Util Re Two Broken Fillet Welds on Pole Shaft Assembly of Circuit Breaker That Energizes Emergency Fire Protection Pumps for Facility. Photographs Attached to 870710 Memo to NRC Encl
Project stage: Other
ML20149M1981988-02-16016 February 1988
Advises That Since Util No Longer Operating Reactor Licensee Due to 870430 Shutdown & 870804 Amend,Modifying License DPR-45 to Possess But Not Operate Status,Generic Ltr 88-01 Determined Inapplicable to Facility
Project stage: Other
3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-4201988-02-23023 February 1988
Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420
Project stage: Other
ML20196H3531988-02-25025 February 1988
Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Ds Series Circuit Breakers Installed at Facility
Project stage: Other
ML20147G8541988-03-0101 March 1988
Responds to NRC Bulletin 88-001 Re Westinghouse Ds Series Circuit Breakers Used in safety-related Applications.Plant Does Not Have Any Westinghouse Ds Series Circuit Breakers
Project stage: Other
ML20147F9981988-03-0404 March 1988
Submits Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Author Does Not Utilize Any Westinghouse Circuit Breakers,As Identified in Subj Bulletin,In Class 1E Applications at Facility
Project stage: Other
ML20150B1821988-03-0707 March 1988
Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breakers in Class 1E Applications So Bulletin 88-001 Does Not Apply to Plant
Project stage: Other
ML20148A8901988-03-0707 March 1988
Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Unit 1 Has No Westinghouse Ds Circuit Breakers Used in Class 1E Application.Unit 2 Reactor Trip & Bypass Breakers Insp Initiated Per Info Notice 87-035
Project stage: Other
ML20150A8991988-03-0909 March 1988
Provides Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Series Ds Circuit Breakers Not Employed at Plant.Insp Required by Bulletin Not Applicable to Plant
Project stage: Other
ML20150C4071988-03-11011 March 1988
Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Type Ds Circuit Breakers Not Used at Plant
Project stage: Other
BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-0011988-03-15015 March 1988
Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001
Project stage: Other
ML20148B6661988-03-16016 March 1988
Responds to 880205 NRC Compliance Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Westinghouse Ds Series Circuit Breakers Not Used in Class IE Svc at Plant
Project stage: Other
NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers1988-03-24024 March 1988
Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers
Project stage: Other
ML20148K2251988-03-25025 March 1988
Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Two Reactor Trip Breakers & Two Reactor Trip Bypass Breakers Subj to Bulletin Used at Millstone Unit 3.Main Pole Shaft Weld Insps Completed by 880225
Project stage: Other
ML20151G7911988-03-28028 March 1988
Confirms That Westinghouse Ds Breakers Not Used at Facility, Per IE Bulletin 88-001, Defects in Westinghouse Circuit Breakers
Project stage: Other
W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin1988-03-29029 March 1988
Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin
Project stage: Other
ML20151A9451988-03-30030 March 1988
Responds to IE Bulletin 88-001 Re Westinghouse Ds/Dsl Circuit Breakers.Ref Components Not Utilized at Facility
Project stage: Other
0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant1988-04-0101 April 1988
Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant
Project stage: Other
ML20151B2021988-04-0404 April 1988
Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Insp of All Westinghouse DS-415 Reactor Trip & Bypass Breakers Completed on 880308 & Results Encl
Project stage: Other
RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant1988-04-0404 April 1988
Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant
Project stage: Other
ML20148Q7241988-04-0707 April 1988
Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Models DS-206,DSL-206, DS-416,DSL-416 or DS-420 Breakers in Class 1E Circuits at Hatch
Project stage: Other
ML20151H7791988-04-0707 April 1988
Informs That Westinghouse Ds Circuit Breakers Not Utilized in Any 1E Application at Plant But Used in non-1E Applications & Will Be Included in Util Preventive Maint Program
Project stage: Other
ML20151E4191988-04-0808 April 1988
Responds to 880205 NRC Bulletin 88-01 Re Defects in Westinghouse Circuit Breakers for Facilities.Westinghouse Ds Series Circuit Breakers Not Used at Plants.Other Provisions of Bulletin Do Not Apply to Plants
Project stage: Other
ML20151E8681988-04-11011 April 1988
Forwards Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers in Class 1E Svc.All Required long-term & short-term Insps Completed
Project stage: Other
ML20151H9651988-04-13013 April 1988
Responds to NRC Bulletin 88-001, Deficiencies in Westinghouse Circuit Breakers. Bulletin Addresses Deficiencies Exclusive to Westinghouse Ds/Dsl Type Circuit Breakers & Outlines Specific Insps to Be Performed
Project stage: Other
ML20151G1151988-04-13013 April 1988
Ack Receipt of in Response to NRC Bulletin 88-001 Re Westinghouse Circuit Breakers.Plant Does Not Use or Plan Use of Circuit Breakers,Therefore Matter Closed
Project stage: Other
ML20205P6881988-04-20020 April 1988
Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Circuit Breakers Subj to Bulletin Installed in Plant
Project stage: Other
ML20155E3921988-06-0909 June 1988
Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit breakers.Sixty-six of sixty-seven Breakers Required New Pole Shafts Due to Failure of Welds to Meet Bulletin Requirements Resulting from Insp
Project stage: Other
ML20150B5261988-06-30030 June 1988
Informs That All Class 1E DS-416 Breakers Now in Use Comply W/Nrc Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers
Project stage: Other
ML20150D3971988-07-0505 July 1988
Advises That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory
Project stage: Other
ML20151E0181988-07-14014 July 1988
Advises That Util 880407 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory
Project stage: Other
ML20151Q9201988-08-0202 August 1988
Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory
Project stage: Other
ML20154D2331988-09-0909 September 1988
Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory & No Further Reply Necessary
Project stage: Other
ML20154E1541988-09-0909 September 1988
Advises That 880408 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory
Project stage: Other
ML20155A4561988-09-29029 September 1988
Requests Addl Info Re Util 880908 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Response Requested within 70 Days of Ltr Date
Project stage: Other
ML20235J1681989-02-17017 February 1989
Advises That 880314 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers Satisfactory. Westinghouse Ds Series Circuit Breakers Not Used in safety-related Applications at Plant
Project stage: Other
ML20235J1651989-02-17017 February 1989
Provides Final Response to NRC Bulletin 88-001, Defects in Westinhouse Circuit Breakers. Alignment Check Specified in 871201 Submittal Satisfactorily Performed During Installation of Replacement Pole Shaft in Breakers
Project stage: Other
ML20247C7191989-05-15015 May 1989
Forwards Supplemental Response to NRC Bulletin 88-001 Re Westinghouse Series Ds Circuit Breakers.Insp Info Corrected
Project stage: Supplement
ML20247K0751989-05-24024 May 1989
Responds to NRC Bulletin 88-001 Re Defects of Westinghouse Circuit Breakers.All forty-seven Westinghouse Type Ds Breakers Inspected Were Found to Have Acceptable Breaker Mechanism Alignment
Project stage: Other
A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage1989-07-24024 July 1989
Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage
Project stage: Other
1988-03-07
[Table View] |
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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:INCOMING CORRESPONDENCE
MONTHYEARML20217D5791999-09-15015 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
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
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)
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
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
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
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-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
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-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
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
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
ML20209H2471999-07-0707 July 1999
Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21
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
ML20209B6851999-06-28028 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl
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
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
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
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
ML20196L2911999-05-19019 May 1999
Forwards Responses to NRC 990315 RAI Concerning GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves
A36791, Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl1999-05-17017 May 1999
Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl
ULNRC-04034, Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions1999-05-17017 May 1999
Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions
05000483/LER-1998-003, Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept1999-05-12012 May 1999
Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept
ML20206Q9551999-05-12012 May 1999
Responds to NRC Re Violations Noted in Insp Rept 50-483/99-04.Corrective Actions:Une Commits to Make Available for NRC Review,Action Plan Outlining Scope & Completion Dates of Project
ULNRC-04027, Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 9905281999-05-0404 May 1999
Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 990528
ML20206E3211999-04-28028 April 1999
Forwards Special Rept 98-03 Re Inservice Insp of CP Sgs,Per Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage.Rept Is Being Resubmitted Due to Typos in Original Rept
ML20206E5781999-04-23023 April 1999
Informs That R Schukai Is No Longer Employed with Amerenue & Info Sent Is No Longer Required.Name Should Be Removed from Mailing Lists.Mailing Label Used by Company Which May Assist in Matter,Submitted
ULNRC-04018, Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date1999-04-21021 April 1999
Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date
ML20205Q7751999-04-16016 April 1999
Forwards Special Rept 98-03 Concerning ISI of Callaway SGs Performed in Apr 1998 During Callaway Plants Ninth Ro. Rept Documents Final SG Insp Results
ULNRC-04015, Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.211999-04-15015 April 1999
Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.21
ULNRC-04005, Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.7901999-04-0707 April 1999
Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.790
ULNRC-04004, Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld1999-04-0707 April 1999
Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld
ULNRC-04007, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date1999-04-0707 April 1999
Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date
ULNRC-04000, Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w)1999-04-0101 April 1999
Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w)
ULNRC-03998, Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.751999-03-30030 March 1999
Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.75
ML20205G2211999-03-25025 March 1999
Submits Rev 28A to Callaway Plant Physical Security Plan, Incorporating Addendum Re Security Sys Replacement Transition Plan,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21
ML20205R5251999-03-25025 March 1999
Forwards Special Rept 98-03 Re Results of Tenth SG Tube Inservice Insp,Per Requirements of Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage
ULNRC-03988, Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 101999-03-19019 March 1999
Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 10
ULNRC-03991, Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette1999-03-19019 March 1999
Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette
ML20204F7211999-03-17017 March 1999
Forwards Amended Fitness for Duty Program Performance Data for Six Month Period Beginning Jul-Dec 1998
ML20204E1331999-03-17017 March 1999
Responds to NRC Re Violations Noted in Insp Rept 50-483/99-02 on 990208-12.Corrective Actions:Will Revise Security Plan to Increase Min Staffing by Three Armed Security Force Response Personnel Per Shift
ML20207C3631999-03-12012 March 1999
Forwards Exam Matl & Associated QA Checklist for Written Exam to Support Plant RO Retake Exam Scheduled for 990423. Exam Matls Requested to Be Withheld from Public Disclosure Until After Exam Completion
05000483/LER-1998-001, Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability1999-03-10010 March 1999
Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability
ULNRC-03979, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date1999-03-0909 March 1999
Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date
ULNRC-03975, Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl1999-03-0505 March 1999
Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl
ULNRC-03971, Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded1999-02-26026 February 1999
Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded
ML20207A4311999-02-17017 February 1999
Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for Period of 980701-981231
1999-09-15
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059G2971990-09-0404 September 1990
Notifies of Implementation of Procedure on 900831 to Correct wide-range Gas Monitor Display for Noble Gas Spectrum
ML20059G4991990-08-30030 August 1990
Forwards Semiannual Radioactive Effluent Release Rept for Jan-Jun 1990 & Rev 0 to APA-ZZ-01003, Odcm
ML20059C3371990-08-23023 August 1990
Advises That Util Plans to Remove Some Thimble Plugging Devices from Plant During Upcoming Refueling Outage.No License Amend Required.Revs to Tech Spec Bases 3/4.2.2 & 3/4.2.3 That Reflect All Removal of Thimble Plugs Encl
ML20058N2051990-08-0707 August 1990
Advises of Implementation of Amend 55,rev to Tech Spec 3/4.7.1.2 Re Auxiliary Feedwater Sys,Effective 900807
ML20081E1971990-07-27027 July 1990
Forwards Rev 6 to Indexing Instruction T210.0002/Q101, Qualification/Certification Documentation & Rev 6 to T210.002/R353, Required Reading/Personnel Form 2
ML20044B1821990-07-0909 July 1990
Forwards Westinghouse Revised Proprietary RCS Flow Measurement Uncertainty Calculation Supplementing Setpoint Studies Submitted in Attachment to Util 900412 Ltr.Encl Withheld
ML20055E5261990-07-0505 July 1990
Forwards Revised marked-up Tech Spec Pages for 900306 Application for Amend to License to Place cycle-specific Core Operating Parameters in Core Operating Limits Rept
ML20055E7861990-07-0505 July 1990
Forwards Callaway Plant 1990 Annual Exercise Scenario on 900530
ML20044A6601990-06-25025 June 1990
Forwards Requested Info Re Seismic Design of safety-related above-ground Vertical Liquid Storage Tanks,Per 900404 Ltr. All Stresses on Tank Roof Angle,Connecting Cylinder to Roof,Remain within Code Allowables Under Postulated Loads
ML20043H8371990-06-21021 June 1990
Forwards Response to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issues at Facility
ML20043H2721990-06-12012 June 1990
Forwards 10CFR50.59 Annual Rept Summaries of Written Safety Evaluations of Changes Approved & Implemented for Plant from 890330 to Present
ML20043E2161990-06-0505 June 1990
Forwards Endorsements 42-48 for Nelia Policy NF-264 & Endorsements 28-34 for Maelu Policy MF-111
ML20043G9331990-06-0404 June 1990
Forwards Rev 13 to Operating QA Manual.
ML20043D7101990-05-31031 May 1990
Forwards NPDES Renewal Application Submitted to State of Mo Dept of Natural Resources on 900518
ML20043B5841990-05-22022 May 1990
Responds to NRC 900423 Ltr Re Violations Noted in Insp Rept 50-483/90-04.Corrective Actions:Security Post Instructions Modified to Require Check of Security Container in QA Area
ML20042F2831990-04-30030 April 1990
Forwards Rev 11 to Inservice Testing Program.
ML20042F1161990-04-30030 April 1990
Provides Clarification to SALP 9 Rept 50-483/90-01 for Sept 1988 - Jan 1990.Licensee Voluntarily Retested Few Remaining Const Workers Originally Approved for Unescorted Access Using mini-IPAT
ML20042F2901990-04-27027 April 1990
Forwards Util 900402 Ltr Documenting Agreement Between State of Mo Historic Preservation Officer & Util Re Cultural Resources
ML20042D8491990-04-0202 April 1990
Forwards Listing of Present Level of Nuclear Property Insurance Coverage & Sources of Insurance,Per 10CFR50.54(w)
ML20012F1601990-03-29029 March 1990
Submits Supplemental Info Re Util Response to Station Blackout.Callaway Will Comply W/Numarc Station Blackout Initiative 5A Re Emergency Diesel Generator
ML20012D1901990-03-19019 March 1990
Forwards Rev 15 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20012D7441990-03-16016 March 1990
Responds to Generic Ltr 89-19 Re Resolution of USI A-47, Safety Implications of Control Sys in LWR Nuclear Power Plants. No Changes or Implementation Schedule Need Be Provided in Response to Generic Ltr 89-19
ML20012C6791990-03-0808 March 1990
Advises That Installation Date for Regulatory Effectiveness Review Concern 2.6.1 Revised to 900531.Deficiency Will Be Under Continuous Surveillance Until Correction Made
ML20012C3111990-03-0606 March 1990
Forwards Addl Info Re Storage of Enriched Fuel in Spent Fuel Pool Area,Per NRC 900216 Request
ML20012B3691990-02-28028 February 1990
Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums
ML20012A4141990-02-23023 February 1990
Requests NRC Concurrence That Leak Chase Sys Is Integral Part of Containment Boundary & Does Not Need to Be Vented During Containment Integrated Leak Rate Test
ML20006E1401990-02-12012 February 1990
Requests Clarification Re Positive Test Results for Controlled Substances,Specifically How Second Confirmed Positive Test Results Are Handled
ML20011E7941990-02-0202 February 1990
Requests Emergency Relief from Tech Spec 3.1.3.1.b Due to Electrical Problem W/Rod Control Sys.Action Required to Prevent Plant Shutdown from 100% Power When Adverse Weather Conditions Exist in Svc Area
ML20006D1061990-01-29029 January 1990
Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Dredge & Visual Shoreline Insps of Missouri River Near Plant Intake Indicated Presence of Small Numbers of Asiatic Clams
ML20006C2311990-01-24024 January 1990
Forwards Callaway Plant Annual Exercise,891011, Emergency Exercise Scenario for 1989 Exercise
ML20006B1371990-01-19019 January 1990
Forwards ECCS Evaluation Model Revs 10CFR50.46 Annual Rept. Util Will Provide Followup Rept Based on Results of Westinghouse Investigation to Be Completed in Second Quarter 1990
ML20005E8161990-01-0303 January 1990
Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of high-hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design
ML20005E5141990-01-0202 January 1990
Certifies That fitness-for-duty Program That Meets Requirements of 10CFR26 Will Be Implemented on 900103
ML20005G3511989-12-28028 December 1989
Forwards Addl Info Supporting NRC Review of Proposed Revs to Tech Spec 3/4.1.3, Movable Control Assemblies.
ML20005E5221989-12-28028 December 1989
Responds to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance.
ML19353B0041989-12-0404 December 1989
Forwards Response to NRC 891016 Ltr Re Results of Regulatory Effectiveness Review on 890918-21.Encl Withheld (Ref 10CFR73.21)
ML19332F1861989-11-30030 November 1989
Responds to Generic Ltr 89-15 Re Emergency Response Data Sys.Sys Will Be Implemented by Jul 1991,to Allow Addl Features to Be Developed for Plant Computer Sys & to Be Installed in Conjunction W/New Plant Computer Sys
ML19332E9881989-11-30030 November 1989
Discusses Visual Insp of Hafnium Rod Cluster Control Assemblies During Refuel-2 in Fall 1987.Results Indicate Guide Card Fretting Wear Per NRC Info Notice 87-019.All Hafnium Rods Replaced W/Silver/Indium/Cadnium Assemblies
ML19332D4441989-11-22022 November 1989
Responds to Generic Ltr 89-21,forwarding Table Providing Implementation Status of Each USI at Facility
ML19327C0741989-11-0707 November 1989
Forwards Executed Amend 3 to Indemnity Agreement B-93, Reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements.
ML19324C4291989-11-0707 November 1989
Responds to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded-Case Circuit Breakers. Bulletin Provisions as Clarified by Suppl Met & Documentation Associated W/Review Being Maintained at Facility
ML19332B6121989-10-31031 October 1989
Provides Individual Plant Exam Method & Schedule.Completion of Level 1 PRA Scheduled for Jul 1991.Containment Performance Analysis Will Be Completed in Feb 1992.Results Will Be Provided in Sept 1992
ML20005D6181989-10-23023 October 1989
Submits Response to Suppl 1 to Generic Ltr 89-07 Re Safeguards Contingency Planning for Surface Vehicle Bombs. Short-term Actions Included to Protect Against Attempted Radiological Sabotage Involving Land Vehicle Bomb
ML19325C9251989-10-0404 October 1989
Submits Corrected Wording to Encl to 890929 Ltr Supporting 10CFR50,App J Exemption to Allow Leak Chase Plugging During Integrated Leak Rate Test
ML20248E4831989-09-29029 September 1989
Forwards Addl Info to Support 10CFR50,App J Exemption to Allow Leaving Leak Chases Plugged During Type a Integrated Leak Rate Test
ML20248G0871989-09-28028 September 1989
Responds to NRC Bulletin 88-011 Re Pressurizer Surge Line Thermal Stratification.Action Items 1.a & B Completed & 1.d Actions Re Stress & Fatigue Ongoing Through Westinghouse Owners Group
ML20248C1951989-09-21021 September 1989
Forwards Summary of Refueling Water Storage Tank Seismic Design Analysis Which Includes Effects of Tank Wall Flexibility.Issue Not Applicable to Condensate Storage Tank at Facility
ML20246J7011989-08-30030 August 1989
Forwards Semiannual Radioactive Effluent Release Rept for First Half 1989.W/o Encl
ML20246K9451989-08-29029 August 1989
Forwards Relief Request 0 to Plant Inservice Insp Program Plan,Per Observations During Refuel III
ML20246E0521989-08-18018 August 1989
Forwards Info on Operator Licensing Exam Schedule,Per Generic Ltr 89-12
1990-09-04
[Table view] |
Text
. _ _ _ _ . . _ _ _ _ __ - -___-_________-__ ___ ____-____ _ _ ____ - _ _ _ - _ _ _ _ _ _ - - _ _ -,
a 1901 Gratet Street, St. Louis Donald F. Schnell Vee Presdent April 11, 1988 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555- ULNRC- 1752 Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT DEFECTS IN WESTINGHOUSE CIRCUIT BREAKERS _(TACS 6_5955f65956) _
Reference:
NRC Bulletin Number 88-01, dated February 5, 1988 NRC Bulletin 88-01 required licensees using Westinghouse series DS circuit breakers in Class lE service to perform and document inspection of the welds on the pole shafts and inspection of the alignment in the breaker closing mechanism.
All of the required long term and short term inspections have been completed and the results are documented in the r.htachments to this letter.
If you have any questions concerning this information, please contact me.
Very truly yours, s -
Donald F. Schnell WEK/pkm Attachments gg\\
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SSR"!J!il**$g3 D ip Mah>g Aadress: P.O. Box 149. St Louis. MO 63166
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STATE OF MISSOURI )
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- CITY OF ST. I4UIS )
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Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Vice Presidenc-Nuclear and an officer of Union Electric Company; that he han read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
\
By D3ha , ,.c ne Vice President Nuclear SUBSCRIBED and sworn to before me this //b day of ,198f.
i A u se AnaBARBARA J. PFAFy n hatARY FUBdC, $1 ATE C; Mts$0VRt
- l . gy gcW4S10N EXPtRES AfRil Ik UI ST Louts COUNTY i
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4 cc Gerald Charnof f , Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.
Washington, D.C. 20037 Dr. J. O. Cermak CFA, Inc.
4 Professional Drive (Suite 110)
Gaithersburg , MD 20879 R. C. Knop Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RR$1 Steedman, Missouri 65077 Tom Alexion (2)
Office of Nuclear Reactor Regulation ;
U.S. Nuclear Regulatory Commission Mail Stop 316 7920 Norfolk Avenue Bethesda, MD 20014 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102
' Attachmsnt 1 ULNRC- 1752 NRC Bulletin 88-01 I_nspectlon_ o,f West _inghouse_ Circuit Breakers NRC Bulletin 88-01 required the inspection of Westinghouse series DS circuit breakers used in Class lE service. Inspection of the welds on the pole shafts and of the alignment in the breaker closing mechanism were to be completed and transmitted to the NRC witin 1) 30 days of completion of the short-term inspections and 2) 30 days of completion of the long-term inspections. The short-term and long-term inspections have been completed at the Callaway Plant and the results are documented herein.
There are eight (8) Westinghouse DS-416 reactor trip breakers at the Callaway Plant; 2 main trip breakers, 2 bypass trip breakers, and 4 spares. These breakers were disassembled and inspected to the requirements described in bulletin 88-01.
Additionally, four replacement shafts were inspected. The results of these inspections are documented in Attachment 2 and summarized below:
- 1) All breakers required or will require corrective action due to the pole shaf t welds not meeting one or more of the weld acceptance cr iteria. All breakers currently in use meet the 6.1.2 criteria, as a minimum. (Shafts meeting G.l.2 criteria are acceptable for up to 4000 cycles with inspections after every 200 cycles of operation.)
- 2) 2 replacecent shafts failed acceptance criteria for replacements and were rejected.
- 3) All of the breakers were inspected for mechanical misalignment, with no failures noted.
Those breakers in use which have a shaf t that failed criteria 6.1.1 but passed criteria 6.1.2 will be replaced at the next available opportunity.
Union Electric concurs with the position on weld porosity acceptance criteria as discussed in Westinghouse's letter to the NRC dated March 1,1988 ( NS-NRC-88-3314) . This letter noted that weld porosity was considered to be a secondary ef fect to weld f atigue strength and that a qualified weld inspector would easily be able to identify and evaluate a weld with high porosity. As such, the NRC criteria is too stringent and the Westinghouse criteria should be considered as an acceptable inspection method.
Page 1 of 2
The staf f time to per form the requested inspections, corrective actions, and associated operability testing is as follows:
!!aintenance Electricians 224 manhours Planning & Scheduling 60 manhours Level III Welding Incpector 50 manhours Maintenance Engineering 80 manhours Welding Engineering and other Management Personnel 15 manhours Page 2 of 2
C
. INSPECTION RESULTS b
POLE SHAFT ASSEMBLY Weld 1 Weld 2 Weld 3 Weld 4 Weld 6 Weld 7 l
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Weld 5
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r 1? ELD WELD INSPECTION ALIGNMENT NUMBER SIZE LENGTH FUSION CRACKS POROSITY OF REMARKS '
BREAKER RTB "BYA", S7N 02YN051B-3, Work Request W106916 Accepted per 6.1.2 Wald 1 3 /16-k 1k" Accept Accept Accept Accept Meets criteria 6.1.1 Accept Accept Failed criteria 6.1.1, met 6.1.2 Wald 2 NYI33 1k" Accept Accept Wald 3 3/16" 1 1/16" Accept Accept Accept Accept Meets criteria 6.1.1 f Wald 4 3f16 1 5/16" Accept Accept Accept Accept Meets criteria 7.1 !
Meets criteria 7.1 exception ;
Wild 5 N/A N/A Accept N/A N/A Accept Wald 6 3/1o -
7/32 1 3/16" Accept Accept Accept Accept Meets criteria 6.1.1 i Weld 7 5/32 1 1/16" Accept Accept Accept Accept Meets criteria 7.1 r Shaft rejected and was replaced with shaft S/N 880-132-7 <
RTB "B" S/N 02YN051B-4, Work Request W110204 (NMR 88100066)
~ Wald 1 1/8" ik Accept Accept Accept Accept Meets criteria 7.1 Accept Failed criteria 6.1.1, met 6.1.2 Ik 1
Umid 2 1/8" Accept Accept Accept 1 1/8 Accept Accept Failed criteria 6.1.1, met 6.1.2 Vald 3 1/8" Accept Accept Wald 4 1/8" 1 5/16 Accept Accept Accept Accept Meets criteria 7.1 Wild 5 N/A N/A Accept N/A N/A Accept Meets criteria 7.1 extension Wild 6 (1/8" 1 1/8 Accept Accept Accept Accept Failed criteria 6.1.1 and 6.1.2 .;
i W21d 7 1/8" 1 3/16 Accept Accept Accept Accept Meets criteria 7.1 l.
t i
i Page 1 of 6 ATTACHMENT 2 ;
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. INSPECTION RESULTS POLE SHAFT ASSEMBLY Weld 1 Weld 2 Weld 3 Weld 4 Weld 6 Weld 7
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WELD INSPECTION ALIGNMENT WELD SIZE LENGTH FtJSION CRACKS POROSITY OF REMARKS NUMBER BREAKER RTB "BYB" S/N 02YN051B-2, Work Request W110207 Accepted per 6.1.2 Wald 1 5/32" 15/16" Accept Acceot Accept Accent Meets criteria 7.1 Failed criteria 6.1.1, met 6.1.2 W2ld 2 $33 1 5/32 Acceot Accept Accept Accept Accept Failed criteria 6.1.1, met 6.1.2 Wald 3 5/32" 1 1/16" Accept Accept Accept Wald 4 1/8" 1 1/16" Accept Accept Accept Accept Meets criteria 7.1 N/A N/A N/A Accept Meets criteria 7.1 exception Wald 5 N/A Accept Weld 6 "$/I6 15/16" Accept Accept Accept Accept Failed criteria 6.1.1, met 6.1.2 _
Wald 7 ldt32 1 1/16" Accept Accept Accept Accept Meets criteria 7.1 Spare Breaker S/N 02YN0583-2 Work Request W431904 Accepted per 6.1.2 1/8 - Meets criteria Wald 1 3/16" 1" Accent AcceSt Accent Accent Wald 2 h)16" 1" Accept Accept Accept Accept Failed criteria 6.1.1 meets 6.1.2 Wald 3 Nf16" 15/16" Accept Accept Accept Accept Failed criteria 6.1.1. meets 6.1.2 W31d 4 5/32" 1" Accept Accept. Accept Accept Meets criteria 7.1 Accept N/A N/A Accept Meets criteria 7.1 exception W21d 5 N/A N/A Failed criteria 6.1.1, meets 6.1.2 Vald 6 5{p$6' 1" Accept Accept Accent Accept lid - Accept Meets criteria 7.1 W2ld 7 5/32 15/16 Accent Accent Accent Page 2 of 6 ATTACHMENT 2
INSPECTION RESULTS POLE SHAFT ASSEMBLY Weld 3 Weld 4 Weld 6 Weld 7 Weld 1 Weld 2
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WELD INSPECTION ALIGNMENT UELD REMARKS CRACKS POROSITY OF NL'MBER SIZE LENGTH FUSION BREAKER Spare Breaker S/N 02YN058B-1 Work Request W106919 (NMR 88100067) Shaft Reiected
-- ----- ----- ----- - - - - - - ------- Not inspected due to failure of #6 Wald 1
- - - - ----- ------- ------- Not inspected due to f ailure of 86 Wald 2 --
----- ------- ------- Not inspected due to f ailure of 86 Wald 3 -- -----
Noeinseect,a N ~ s u i n., 4, #6 Wild 4 -- ----- ----- ----
U21d 5 -- ----- ----- - - - - ------- ------- Not inseected due en fuluvo nr u
- - - - - - ------- Failed criteria 6.1.1 and 6.1.2 Wald 6 (1/8" ----- ----- -----
Not inspected due to failure of #6 Wald 7 Spare Breaker S/N 02N058B-3 Accepted per 6.1.2 Accept Accept Meets criteria 7.1 Wald 1 1/8" 7/8" Accept Accept Failed criteria 6.1.1, met 6.1.2 Accept Accept Accept Accept Weld 2 1/8" 1" Accept Accept Meets criteria 6.1.1 Celd 3 3/16" 1\" Accept Accept 1" Accept Accept Accept Accept Meets criteria 7.1 Wald 4 3/16" N/A Accept Meets criteria 7.1 exception N/A N/A Accept N/A Weld 5 Failed criteria 6.1.1, met 6.1.2 Accept Accept Accept Accept W21d 6 1/8" l" Accept Accept Accept Meets criteria 7.1 U21d 7 1/8" 7/8" Accept o
Page 3 of 6 ATTACHMENT 2
- INSPECTION RESULTS POLE SHAFT ASSEMBLY Weld 1 Weld 2 Weld 3 Weld 4 Weld 6 Weld 7
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WELD WELD INSPECTION ALIGNMENT NUMBER SIZE LENGTH FUSION CRACKS POROSITY OF REMARKS BREAKER Shaft Rejected and Was Replaced RTB "A" S7N 02YN0513-1. Work Request W110205 (NMR 88I00054) With Shaf t From SA'02YN058B-2 Uald 1 ---- ----- ------ ----- ------- ------- Not inspected due to failure of #7 Wald 2 --- ----- ------ ---- - - - - ------- Not inspected due to failure of #7 Wild 3 ---- ----- ------ ----- ------- ------- Not inspected due to failure of #7 Wald 4 ---- ----- ------ ----- ------- - - - - - - Not inspected due to failure of #7 Wald 5 ---- ----- ------ - - - - ------- ------- Not inspected due to failure of #7 Wald 6 ---- ----- - - - - - ----- - - - - - - - - - - - Not inspected due to failure of #7 Wald 7 41/8 ----- reject ----- - - - - - - ------- Failed 7.1 Replacement Shaft Rejected, 32' Spare Breaker S/N 02YN058B-4, Work Request W110206 (NMR 88I00072)
~ Wald 1 1/8" 7/8 Accept Accept Accept Accept Me.:ts criteria 7.1 Wald 2 < 1/8" 15/16" Accept Accept Accept Accept Failed criteria 6.1.1 and 6.1.2 Wald 3 ( 1/8" 3/4" Accept Accept Accept Accept Failed criteria 6.1.1 and 6.1.2 L/6 - Failed criteris 6.1.1 .snd 6.1.2 U21d 4 3/16" 3/4" Accept Accent Accept Accept N/A N/A Accept Meets criteria 7 i exception Wald 5 N/A N/A Accept Weld 6 1/8" 11/16" Accept Accept Accept Accept Failed criteria 6.1.1 and 6.1.2 L/o - Cold W21d 7 3/10 ' 3/8" St3rt & Accent Accent Accent Filled criteria 7.1 stop Page 4 of 6 ATTACHMENT 2
INSPECTION RESULTS POLE SHAFT ASSEMBLY 4
l l Weld 1 Veld 2 Weld 3 Weld 4 Weld 6 Weld 7
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WELD WELD INSPECTION ALIGNMENT N1'MBER SIZE LENGTH F1)SION CRACKS POROSITY OF REMARKS BREAKER 1
Replacement Shaft S/N 880-132-6 Shaft Accepted - Meets Criteria Weld 1 Accept Accept Accept Accept Accept N/A Meets 7.1 Weld 2 Accept Accept Accept A: cept Accept N/A Meets 6.1.1 Meets 6.1.1 l Wald 3 Accept Accept Accept Accept Accept N/A W21d 4 Accept Accept Accept Accept Accept N/A Meets 7.1 Wild 5 N/A N/A Accept N/A N/A N/A Meets 7.1 exception Wald 6 Accept Accept Accept Accept Accept N/A Meets 6.1.1 W21d 7 Accept Accept Accept Accept Accept N/A Meets 7.1 Replacement Shaft S/N 880-132-7, Shaft Accepted - Meets Criteria Vald 1 Accept l Accept Accept Accept Accept N/A Meets 7.1 Wild 2 Accept Accept Accept Accept Accept N/A Meets 6.1.1 U21d 3 Accept Accept Accept Accept Accept N/A Meets 6.1.1 Wald 4 Accept Accept Accept Accept Accept N/A Meets 7.1 W21d 5 N/A N/A Accept N/A N/A N/A Meets 7.1 exception W.1d 6 Accept Accept Accept Accept Accept N/A Meets 6.1.1 aid 7 Accept Accept Accept Accept Accept N/A Meets 7.1 Page 5 of 6 ATTACHMENT 2
e INSPECTION RESULTS I i
- l POLE SHAFT ASSEMBLY Weld 1 Weld 2 Weld 3 Weld 4 Weld 6 Weld 7 1
bd e 5 c, 7-/
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1 1.rE1.D WELD INSPECTION ALIGhMENT 4
NUMBER SIZE LENGTH FUSION CRACKS POROSITY OF REMARKS BREAKER
- Replacement Shaft S/N 880-132-1, hKR 88100059 Shaft Rejected and Returned to Westinghouse i
Wald 1 1/8" 1 5/16" Accept Accept Accept N/A Meets criteria 7.1 N/A Failed criteria 6.1.1, met 6.1.2 t7 eld 2 1/8" 1 3/8" Accept Accept Accept l Unid 3 1/8" ik" Efkht Accept Accept N/A kk*kt N h d" see 4,T Y 8
! W2ld 4 1/8" 1 3/16" Accept Accept Accept N/A Meets criteria 7.1 N/A N/A N/A N/A Meets criteria 7.1 exception j Wald 5 N/A Accept N/A Failed criteria 6.1.1, met 6.1.2
! 17 eld 6 1/8" 1 3/16" Accept Accept Accept l Vald 7 3/16 1 5/16" Accept Accept Accept i N/A Meets criteria 7.1 J
Replacement Shaft S/N 880-132-2, NMR 88100059, Shaft Rejected and Returned to Westinghouse
~ Unid 1 1/8" th" Accept Ae:ept Accept N/A Meets criteria 7.1 Accept N/A Failed criteria 6.1.1, met 6.1.2 l Wald 2 1/8" 1 7/16" Accept Accept Accept N/A Failed criteria 6.1.1, met 6.1.2
) U21d 3 1/8" 1 9/16" Accept Accept I
Wald 4 1/8" 1 3/8" Accept Accept Accept N/A Meets criteria 7.1 N/A N/A Meets criteria 7.1 exception Wald 5 N/A N/A Accept N/A l Failed cri:eria 6.1.1, met 6.1.2 N/A I
Wald 6 1/8" ik" Accept Accept Accept start and stop
- Exygdin co Wald 7 3/16 1 3/8" Acceptr Accept Accept N/A . , ,
l l
I l
Page 6 of 6 ATTACHMENT 2 l
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