ML20195C513
Letter Sequence Other | |
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TAC:M98803, Modify Section 3.8 Mode Restriction Notes, TSTF-36, Battery Float Current and Battery Inspection Program, TSTF-38 (Approved, Closed) | |
Initiation
Questions
Answers Results Other: ML20195C513, ML20196K726, ML20236K821, ML20236S240, ML20236T131, ULNRC-03889, Forwards Proposed Tech Specs Sections 1.0,2.0 & 3.0, Converting to Improved Tech Specs,In Response to NRC 980707 & 09 Rais.Response to Comment Number 1.1-4 Will Be Provided Separately After 980817 NRC Ltr to NEI Has Been Evaluated, ULNRC-03937, Responds to RAIs on Proposed Conversion to Its,Section 3.8, Electrical Power Sys, ULNRC-03946, Forwards RAI Re Proposed Conversion to Improved Tech Specs Sections 1.0,3.1,3.2,3.3,3.4,3.7,3.9 & 5.0.Suppl to Ref Will Be Provided at Later Date, 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 Date, 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 Date, 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 Date, WO 10-0066, Correction of Typographical Error in Technical Specification 5.7.2 | |
MONTHYEARML20148P0961997-06-25025 June 1997
[Table View]Summary of 970603 Meeting W/Wcnoc Staff to Discuss Status of Licensing Actions Currently Under Review by NRR & to Discuss Any Upcoming Requests That Licensee Has Identified Project stage: Meeting ML20248A1211998-05-22022 May 1998 Forwards Request for Addl Info Re 970515 Proposed License Amend to Convert Current TSs for Comanche Peak Steam Electric Station,Units 1 & 2 to Improved Standard TS Project stage: RAI ML20248E8441998-05-22022 May 1998 Forwards RAI on Proposed Conversion to Improved Std TS for Plant,Unit 1 in Section 3.6.Response Requested within 30 Days of Date of Ltr Project stage: RAI ML20248F1881998-05-22022 May 1998 Forwards Request for Addl Info on Proposed Conversion to Improved Standard TSs for Wolf Creek Nuclear Generating Station,Unit 1 Project stage: RAI ML20249B4571998-06-16016 June 1998 Forwards Request for Addl Info Re Licensee Amend to Convert Current TS for Callaway Plant,Unit 1 to Improved Ts,Provided by Project stage: RAI ML20249B5771998-06-16016 June 1998 Refers to WCNOC 970515 Proposed License Amend to Convert Current TS for Unit 1 to Improved Sts.Licensee Should Responds to Encl RAI within 30 Days of Ltr Date Project stage: RAI ML20249B0121998-06-17017 June 1998 Forwards RAI Re Proposed Conversion to Improved Std TSs for Plant,Units 1 & 2.Response Requested within 30 Days of Receipt of Ltr Project stage: RAI ML20249B5041998-06-17017 June 1998 Forwards Request for Addl Info on Proposed License Amend to Convert Current TS for Wolf Creek Nuclear Generating Station,Unit 1 to Improved Standard TS Project stage: RAI ML20249B5301998-06-17017 June 1998 Forwards Request for Addl Info on 970515 Proposed License Amend to Convert Current TSs for Callaway Plant,Unit 1 to Improved Standard TSs Project stage: RAI ULNRC-03853, Forwards Info & TS Pages Re 980522 Application for Amend to License NPF-30,converting to Improved Sts,In Response to NRC Request for Addl Info.Suppl to Util Will Be Provided at Later Date1998-06-26026 June 1998 Forwards Info & TS Pages Re 980522 Application for Amend to License NPF-30,converting to Improved Sts,In Response to NRC Request for Addl Info.Suppl to Util Will Be Provided at Later Date Project stage: Request ML20236K8211998-07-0707 July 1998 Requests Addl Info on Proposed Conversion to Improved Std Tss.Response Requested within 30 Days of Date of Ltr Project stage: Other ML20236L3011998-07-0707 July 1998 Forwards RAI Re Proposed Conversion to Improved Std Plant,Unit 1.Addl Info Needed in Section 2.0, Safety Limits & Section 3.0, Limiting Condition for Operation Applicability/Surveillance Requirement Applicability Project stage: RAI ML20236K8121998-07-0707 July 1998 Requests Addl Info Based on Review of Selected Portions of Application.Addl Info Needed in Section 2.0,safety Limits & Section 3.0,limiting Condition for Operation Applicability Surveillance Requirement Applicability Project stage: Approval ML20236P1621998-07-0909 July 1998 Forwards RAI Re Proposed License Amend to Convert Current TSs for Plant,Unit 1 to Improved Tss,Per 970515 Request. Response Requested within 30 Days of Receipt of Ltr Project stage: RAI ML20236P3091998-07-0909 July 1998 Forwards RAI Re Proposed Conversion to Improved TS for Plant,Unit 1.Addl Info Needed in Section 1.0, Use & Application. Response Requested within 30 Days of Receipt of Ltr Project stage: RAI ML20236R3021998-07-14014 July 1998 Forwards Request for Addl Info Re Proposed Conversion to Improved Std TS for Plant,Units 1 & 2 Project stage: RAI ML20236Q6671998-07-15015 July 1998 Forwards Request for Addl Info on Proposed Conversion to Improved Standard TSs for Wolf Creek Nuclear Generating Station,Unit 1 Project stage: RAI ML20236Q6711998-07-15015 July 1998 Forwards Request for Addl Info on Proposed Conversion to Improved Standard TSs for Callaway Plant,Unit 1 Project stage: RAI ML20236R0431998-07-15015 July 1998 Forwards Request for Addl Info on Proposed Conversion to Improved Standard TSs for Comanche Peak Steam Electric Station,Units 1 & 2 Project stage: RAI ML20236S2391998-07-17017 July 1998 Forwards RAI Re Proposed License Amend to Convert Current TSs for Plant,Unit 1 to Improved Std Tss.Addl Info Needed in Section 3.3, Instrumentation Project stage: RAI ML20236T1311998-07-17017 July 1998 Requests Addl Info on Util Proposed License Amend to Convert Current TSs for Plant,Units 1 & 2 to Improved Std Tss.Addl Info Needed in Section 3.3, Instrumentation Project stage: Other ML20236S2401998-07-17017 July 1998 Requests Addl Info on Proposed License Amend to Convert Current TS to Improved Standard TS for Callaway Plant, Unit 1 Project stage: Other ML20236S1991998-07-21021 July 1998 Forwards RAI Re Proposed Conversion to Improved Std TSs for Plant,Unit 1.Response Requested within 30 Days of Date of Ltr Project stage: RAI ML20236S2201998-07-21021 July 1998 Forwards RAI Re Util Proposed License Amend to Convert Current TSs for Plant,Unit 1 to Improved Tss.Response Requested within 30 Days of Receipt of Ltr Project stage: RAI ML20236T1871998-07-22022 July 1998 Forwards RAI on Proposed Conversion to Improved Std TSs for Plants,Units 1 & 2,per .Response Requested within 30 Days of Date of Ltr Project stage: RAI ULNRC-03877, Submits Response to NRC RAI Re Proposed Conversion to Improved TSs Sections 3.1,3.2,3.5,3.9 & 4.0.Suppl to Will Be Provided at Later Date1998-08-0404 August 1998 Submits Response to NRC RAI Re Proposed Conversion to Improved TSs Sections 3.1,3.2,3.5,3.9 & 4.0.Suppl to Will Be Provided at Later Date Project stage: Response to RAI ML20237C4211998-08-14014 August 1998 Forwards RAI Re 970515 Proposed License Amend to Convert IST for Wcgs,Unit 1 to Improved Std Ts.Response Requested within 30 Days of Date of Ltr Project stage: RAI ML20237C4251998-08-14014 August 1998 Forwards RAI Re Proposed License Amend to Convert Current TSs for Plant,Unit 1 to Improved Std Ts,Per 970515 Request. Response Requested within 30 Days of Date of Ltr Project stage: RAI ML20237C4401998-08-14014 August 1998 Forwards RAI Re 970515 Proposed License Amend to Convert Current TSs for Plant,Units 1 & 2 to Improved Std Tss. Response to Questions Pertaining Plant,Units 1 & 2 Requested within 30 Days of Date of Ltr Project stage: RAI ULNRC-03889, Forwards Proposed Tech Specs Sections 1.0,2.0 & 3.0, Converting to Improved Tech Specs,In Response to NRC 980707 & 09 Rais.Response to Comment Number 1.1-4 Will Be Provided Separately After 980817 NRC Ltr to NEI Has Been Evaluated1998-08-27027 August 1998 Forwards Proposed Tech Specs Sections 1.0,2.0 & 3.0, Converting to Improved Tech Specs,In Response to NRC 980707 & 09 Rais.Response to Comment Number 1.1-4 Will Be Provided Separately After 980817 NRC Ltr to NEI Has Been Evaluated Project stage: Other ML16342A7091998-08-28028 August 1998 Summary of 980811-14 Meeting with Utils Re Requests for Addl Info from NRC Staff on Licensees Application for Conversion of Current Plant TSs to Improved Tss.List of Attendees & Handouts Provided by NRC Encl Project stage: Meeting ML20151U9281998-09-0303 September 1998 Forwards Request for Addl Info Re Util Proposed License Amend to Convert TSs for Wolf Creek Nuclear Generation Station,Unit 1 to Improved Standard Tss, Project stage: RAI ML20151U9221998-09-0303 September 1998 Forwards Request for Addl Info Re Util Proposed License Amend to Convert Current TSs for Callaway Plant,Unit 1 to Improved Standard Tss, Project stage: RAI ML20239A2821998-09-0303 September 1998 Forwards RAI Re Proposed License Amend to Convert Current TSs for Plant,Units 1 & 2,to Improved Std Tss.Response Info Needed in Section 3.8 & Subsections 3.4 Through 3.8. Response Requested within 30 Days of Date of Ltr Project stage: RAI ULNRC-03900, Forwards Response to NRC 980715 & 0721 RAIs Re Util 970515 Application for Amend to License NPF-30 to Convert to Improved TS Sections 3.4 & 5.01998-09-24024 September 1998 Forwards Response to NRC 980715 & 0721 RAIs Re Util 970515 Application for Amend to License NPF-30 to Convert to Improved TS Sections 3.4 & 5.0 Project stage: Request ML20154J0101998-10-0707 October 1998 Forwards RAI Re Licensee Proposed Amend to Convert Current TSs for Plant,Unit 1 to Improved Std Ts.Addl Info Required in Section 3.8,Subsections 3.8.1,3.8.2,3.8.3,3.8.9 & 3.8.10. Response Requested within 30 Days of Date of Ltr Project stage: RAI ML20154J0061998-10-0707 October 1998 Forwards RAI Re Licensee Proposed Amend to Convert Current TSs for Plant,Unit 1 to Improved Std Tss.Addl Info Needed in Section 3.8,Subsections 3.8.1,3.8.2,3.8.3 & 3.8.9.Response Requested within 30 Days of Date of Ltr Project stage: RAI ML20154G3421998-10-0707 October 1998 Forwards Request for Addl Info Re Proposed Conversion to Current TS for CPSES Units 1 & 2 to Improved Ts.Response Requested within 30 Days of Ltr Date Project stage: RAI ML16342A5551998-10-16016 October 1998 Summary of 980915-18 Meeting with Listed Participants to to Discuss Staff RAIs on Licensee Application for Conversion of Current TSs to Improved TS for Listed Facilities.List of Attendees Encl Project stage: RAI ULNRC-03905, Forwards Response to RAI on Proposed Conversion to Improved TS Section 3.7, Plants Sys1998-10-21021 October 1998 Forwards Response to RAI on Proposed Conversion to Improved TS Section 3.7, Plants Sys Project stage: Response to RAI ULNRC-03908, Forwards Response to NRC RAI Re Proposed Amend to License NPF-30,converting to Improved Tech Specs.Proposed Sections 3.1,3.2,3.4,3.5 & 5.0 Also Encl1998-10-21021 October 1998 Forwards Response to NRC RAI Re Proposed Amend to License NPF-30,converting to Improved Tech Specs.Proposed Sections 3.1,3.2,3.4,3.5 & 5.0 Also Encl Project stage: Response to RAI ML16342A5701998-11-0606 November 1998 Summary of 981013-14 Meeting with Listed Attendees to Discuss Licensee Responses to Staff RAI on Licensee Application for Conversion of Current TSs to Improved TSs for Listed Facilities.Nrc Staff Handouts Encl Project stage: RAI ULNRC-03927, Forwards Response to NRC RAI Re TS Section 3.3, Instrumentation, Converting to Improved Tech Specs. Requested Info Is Encl as Well as Any Addl Changes Needed for Section 3.3 as Identified by Licensee1998-11-25025 November 1998 Forwards Response to NRC RAI Re TS Section 3.3, Instrumentation, Converting to Improved Tech Specs. Requested Info Is Encl as Well as Any Addl Changes Needed for Section 3.3 as Identified by Licensee Project stage: Response to RAI ULNRC-03937, Responds to RAIs on Proposed Conversion to Its,Section 3.8, Electrical Power Sys1998-12-11011 December 1998 Responds to RAIs on Proposed Conversion to Its,Section 3.8, Electrical Power Sys Project stage: Other ULNRC-03946, Forwards RAI Re Proposed Conversion to Improved Tech Specs Sections 1.0,3.1,3.2,3.3,3.4,3.7,3.9 & 5.0.Suppl to Ref Will Be Provided at Later Date1998-12-22022 December 1998 Forwards RAI Re Proposed Conversion to Improved Tech Specs Sections 1.0,3.1,3.2,3.3,3.4,3.7,3.9 & 5.0.Suppl to Ref Will Be Provided at Later Date Project stage: Other ML20206U6131999-02-0202 February 1999 Forwards Draft SER on Proposed Conversion of Current TSs for Wolf Creek Generating Station to Improved Tss.Encl Draft SER Being Provided for Review to Verify Accuracy & to Prepare Certified Improved TSs Project stage: Draft Approval ML20203C5271999-02-0505 February 1999 Forwards follow-up Items Re Proposed Conversion to Improved TS Sections 1.0,3.2,3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Submittal Not Supplement to 970517 Amend Request & Not Reviewed by Onsite Review Committee or Nuclear Safety Review Board Project stage: Supplement 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 Project stage: Other ML20196K7261999-03-26026 March 1999 Forwards Certified Copy of ITS & ITS Bases,As Committed in Licensee to Nrc.Summary of Editorial Corrections, Also Encl Project stage: Other 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 Project stage: Other 1998-07-17 |
ML20195C513 | |
Person / Time | |
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Site: | Callaway, Cherokee |
Issue date: | 05/28/1999 |
From: | Passwater A UNION ELECTRIC CO. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
Shared Package | |
ML20195C516 | List: |
References | |
TAC-M98803, ULNRC-4043, NUDOCS 9906080206 | |
Download: ML20195C513 (4) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K1051999-10-19019 October 1999
[Table view]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 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 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 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 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-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-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 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 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 1999-09-22 Category:INCOMING CORRESPONDENCE MONTHYEARML20217D5791999-09-15015 September 1999
[Table view]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 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 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 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 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 A93443, Forwards Responses to NRC 990315 RAI Concerning GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-05-19019 May 1999 Forwards Responses to NRC 990315 RAI Concerning GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves 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 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 05000483/LER-1998-003-01, 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-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-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-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-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 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 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 ML20204F7211999-03-17017 March 1999 Forwards Amended Fitness for Duty Program Performance Data for Six Month Period Beginning Jul-Dec 1998 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 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 ML20207C3461999-02-16016 February 1999 Forwards Exam Outline & Associated QA Checklist for Written Exam to Support Plant RO Retake Exam Scheduled 990423.Please Withhold Exam Matls from Public Disclosure Until After Exam Completion ML20203C5271999-02-0505 February 1999 Forwards follow-up Items Re Proposed Conversion to Improved TS Sections 1.0,3.2,3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Submittal Not Supplement to 970517 Amend Request & Not Reviewed by Onsite Review Committee or Nuclear Safety Review Board ML20202F7721999-01-29029 January 1999 Provides Changes to Further Clarify That Electrosleeve Use Is Limited to 2 Cycles Following Installation of First Electrosleeve 1999-09-15 |
Text
f Union 0;rtric One Ameren Plaza 1901 Chouteau Avenue PO Box 66149 St. Louis, MO 63166.6149 314 621.3221 9
J May 28,1999 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station Pl-137 Washington, D.C. 20555-0001 Gentlemen:
ULNRC-4043 TAC NO. M98803 WAmean DOCKET NUMBER 50-483 CALLAWAY PLANT UNION ELECTRIC COMPANY FOLLOW-UP ITEMS RELATED TO THE PROPOSED CONVERSION TO THE IMPROVED TECHNICAL SPECIFICATIONS SECTIONS 3.9 AND 5.6
Reference:
ULNRC-4044 dated May 27,1999 Union Electric is providing the attached revisions to Sections 3.9 and 5.6 of the Improved Technical Specifications. Following additional reviews by the staff, these revisions are based on resolution telecons held between the NRC staff and AmerenUE personnel on May 26 and 27,1999.
As documented on the attached pages, the Specification 3.9.1, (boron concentration requirements in the refueling pool), is revised to maintain the CTS requirements on refueling pool boron concentration limits. By this change, DOC 01-02-LG (ITS Section 3.9) does not relocate the limits for boron concentration to the COLR, and DOC 01-04-LG (ITS Section 3.9) does not relocate the Ng limit to the bases. Therefore, these DOCS are not applicable for Callaway. Note that references to the Lalimit and also to the COLR remain in the Bases. However, these references have been revised to reflect the fact that the limits are maintained in the LCO, consistent with the CTS. For the aid of the operators, the limit for the boron concentration is presented in the COLR.
In addition to the above revision, Section 5.6.5, CORE OPERATING LIMITS REPORT (COLR), is revised to delete item 5.6.5.a (8). This value as a limit, is controlled under the LCO of Specification 3.9.1, and is merely provided in the COLR as a convenient reference for the operators. Because the refueling boron concentration limit remains in the LCO, consistent with CTS, DOC 3-15-M (ITS Section 5.0) does not relocate the limit to the COLR, and the DOC is no longer applicable for Callaway.
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.i U.S. Nuclear Regulatory Commission May 28,1999 Page 2 Section 5.6.6, Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PLTR), is revised to add a reference to Callaway Amendment No.124, dated April 2,1998. This reference documents that NRC has reviewed and approved the analytical methods used to generate this report specifically for Callaway.
Finally, these revised ITS pages should replace those transmitted to the referenced letter as indicated on the Attachment cover sheet.
Please contact us if you have any questions.
Very truly yours, M
A Alan C. Pas %4 x
swater F
Manager, Corporate Nuclear Services DJW/jdg Attachments i
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1 1
STATE OF MISSOURI )
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David'Shafer, of lawful age, being first duly sworn upon oath says that he is Supervising Engineer, Corporate Nuclear Services, Reguletory Operations for Union Electric company; that he has 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 h8
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David Shafer' Supervising Engineer, Regulatory Operations, Corporate Nuclear Services SUBSCRIBED.and sworn to before me this
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'2 day of 7/74r/
1999.
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M. H.
Fletcher l
Professional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20855-2432 Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road I
Steedman, MO 65077 Mr. Mel Gray (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E16 11555 Rockville Pike Rockville, MD 20852-2738 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 Ron Kucera Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Denny Buschbaum TU Electric P.O. Box 1002 i
Glen Rose, TX 76043 j
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Pat Nugent Pacific Gas & Electric j
Regulatory Services
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P.O. Box 56 Avila Beach, CA 93424 i