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| | number = ML20212A358 | | | number = ML20212A358 |
| | issue date = 09/13/1999 | | | issue date = 09/13/1999 |
| | title = Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Dtd 990709 Meets Condition 2,as Stated in 970509 NRC Ltr | | | title = Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr |
| | author name = Skay D | | | author name = Skay D |
| | author affiliation = NRC (Affiliation Not Assigned) | | | author affiliation = NRC (Affiliation Not Assigned) |
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| | contact person = | | | contact person = |
| | document report number = TAC-MA6091, NUDOCS 9909160169 | | | document report number = TAC-MA6091, NUDOCS 9909160169 |
| | | title reference date = 07-09-1999 |
| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 4 | | | page count = 4 |
| | | project = TAC:MA6091 |
| | | stage = Other |
| }} | | }} |
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| ==Dear Mr. Kingsley:== | | ==Dear Mr. Kingsley:== |
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| By letter dated July 9,1999, Commonwealth Edison Company (Comed) provided Siemens Power Corporation (SPC) fuel and General Electric (GE) fuel Minimum Critical Power Ratio data for LaSalle County Station, Unit 1, Cycle 9. This data was sent in response to an NRC letter and safety evaluation relating to the SPC licensing topical report EMF-1125(P)(A), | | By {{letter dated|date=July 9, 1999|text=letter dated July 9,1999}}, Commonwealth Edison Company (Comed) provided Siemens Power Corporation (SPC) fuel and General Electric (GE) fuel Minimum Critical Power Ratio data for LaSalle County Station, Unit 1, Cycle 9. This data was sent in response to an NRC letter and safety evaluation relating to the SPC licensing topical report EMF-1125(P)(A), |
| "ANFB [ Advanced Nuclear Fuel for Boiling Water Reactors) Critical Power Correlation Application for Co-Resident Fuel," Supplement 1, Appendix C, dated May 9,1997, in its July 9, 1999, letter, Comed requested written confirmation that the data provided satisfies the condition of the NRC letter. The staff confirms that the data provided does meet Condition 2 as i stated in the May 9,1997, letter. ; | | "ANFB [ Advanced Nuclear Fuel for Boiling Water Reactors) Critical Power Correlation Application for Co-Resident Fuel," Supplement 1, Appendix C, dated May 9,1997, in its {{letter dated|date=July 9, 1999|text=July 9, 1999, letter}}, Comed requested written confirmation that the data provided satisfies the condition of the NRC letter. The staff confirms that the data provided does meet Condition 2 as i stated in the {{letter dated|date=May 9, 1997|text=May 9,1997, letter}}. ; |
| Sincerely, Original signed by: | | Sincerely, Original signed by: |
| l Donna M. Skay, Project Manager, Section 2 Project Directorate ill Q91gog pgg73 Division of Licensing Project Management p PDR Office of Nuclear Reactor Regulation | | l Donna M. Skay, Project Manager, Section 2 Project Directorate ill Q91gog pgg73 Division of Licensing Project Management p PDR Office of Nuclear Reactor Regulation |
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| ==Dear Mr. Kingsley:== | | ==Dear Mr. Kingsley:== |
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| By letter dated July 9,1999, Commonwealth Edison Company (Comed) provided Siemens Power Corporation (SPC) fuel and General Electric (GE) fuel Minimum Critical Power i Ratio data for LaSalle County Station, Unit 1, Cycle 9. This data was sent in response to an I | | By {{letter dated|date=July 9, 1999|text=letter dated July 9,1999}}, Commonwealth Edison Company (Comed) provided Siemens Power Corporation (SPC) fuel and General Electric (GE) fuel Minimum Critical Power i Ratio data for LaSalle County Station, Unit 1, Cycle 9. This data was sent in response to an I |
| NRC letter and safety evaluation relating to the SPC licensing topical report EMF-1125(P)(A), j | | NRC letter and safety evaluation relating to the SPC licensing topical report EMF-1125(P)(A), j |
| ~ "ANFB [ Advanced Nuclear Fuel for Boiling Water Reactors) Critical Power Correlation j Application for Co-Resident Fuel," Supplement 1, Appendix C, dated May 9,1997. In its July 9, 1999, letter, Comed requested written confirmation that the data provided satisfies the condition of the NRC letter. The staff confirms that the data provided does meet Condition 2 as stated in the May 9,1997, letter. | | ~ "ANFB [ Advanced Nuclear Fuel for Boiling Water Reactors) Critical Power Correlation j Application for Co-Resident Fuel," Supplement 1, Appendix C, dated May 9,1997. In its {{letter dated|date=July 9, 1999|text=July 9, 1999, letter}}, Comed requested written confirmation that the data provided satisfies the condition of the NRC letter. The staff confirms that the data provided does meet Condition 2 as stated in the {{letter dated|date=May 9, 1997|text=May 9,1997, letter}}. |
| Sincerely, ! | | Sincerely, ! |
| Original signed by: | | Original signed by: |
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| ==Dear Mr. Kingsley:== | | ==Dear Mr. Kingsley:== |
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| l By letter dated July 9,1999, Commonwealth Edison Company (Comed) provided Siemens Power Corporation (SPC) fuel and General Electric (GE) fuel Minimum Critical Power Ratio data for LaSalle County Station, Unit 1, Cycle 9. This data was sent in response to an NRC letter and safety evaluation relating to the SPC licensing topical report EMF-1125(P)(A), | | l By {{letter dated|date=July 9, 1999|text=letter dated July 9,1999}}, Commonwealth Edison Company (Comed) provided Siemens Power Corporation (SPC) fuel and General Electric (GE) fuel Minimum Critical Power Ratio data for LaSalle County Station, Unit 1, Cycle 9. This data was sent in response to an NRC letter and safety evaluation relating to the SPC licensing topical report EMF-1125(P)(A), |
| "ANFB [ Advanced Nuclear Fuel for Boiling Water Reactors) Critical Power Correlation Application for Co-Resident Fuel," Supplement 1, Appendix C, dated May 9,1997, in its July 9, 1999, letter, Comed requested written confirmation that the data provided satisfies the condition of the NRC letter. The staff confirms that the data provided does meet Condition 2 as | | "ANFB [ Advanced Nuclear Fuel for Boiling Water Reactors) Critical Power Correlation Application for Co-Resident Fuel," Supplement 1, Appendix C, dated May 9,1997, in its {{letter dated|date=July 9, 1999|text=July 9, 1999, letter}}, Comed requested written confirmation that the data provided satisfies the condition of the NRC letter. The staff confirms that the data provided does meet Condition 2 as |
| ! stated in the May 9,1997, letter. . | | ! stated in the {{letter dated|date=May 9, 1997|text=May 9,1997, letter}}. . |
| Sincerely, l & 1 Donna M. Skay, Project Manager, ection 2 I' Project Directorate lll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 cc: See next page I | | Sincerely, l & 1 Donna M. Skay, Project Manager, ection 2 I' Project Directorate lll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 cc: See next page I |
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MONTHYEARML20212A3581999-09-13013 September 1999
Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr
Project stage: Other
1999-09-13
[Table View] |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999
Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl
ML20217H6341999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld
ML20217H6251999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld
ML20217F4301999-10-14014 October 1999
Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1
ML20217D3191999-10-12012 October 1999
Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon
ML20217C1671999-10-0808 October 1999
Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2
ML20217A7601999-10-0606 October 1999
Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy
ML20212M0931999-10-0404 October 1999
Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff
05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999
Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl
ML20217A6201999-09-30030 September 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl
ML20216J8241999-09-30030 September 1999
Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr
ML20212E7171999-09-22022 September 1999
Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads
05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999
Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl
ML20212C0591999-09-17017 September 1999
Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97
ML20212A3581999-09-13013 September 1999
Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr
ML20211Q9911999-09-10010 September 1999
Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring
ML20212A1141999-09-10010 September 1999
Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage
ML20211P2211999-09-0808 September 1999
Forwards Insp Repts 50-373/99-14 & 50-374/99-14 on 990809- 13.No Violations Noted.Insp Concluded That Emergency Preparedness Program Maintained in Good State of Operational Readiness
ML20212A8571999-09-0707 September 1999
Informs That Proprietary Document, Power Uprate SAR for LaSalle County Station,Units 1 & 2, Rev 2,Class III, NEDC-32701P,submitted in ,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20211Q6861999-09-0606 September 1999
Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant License Applicants During Wks of 001113 & 20. Validation of Exam Will Occur at Station During Wk of 001023
05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl
ML20211M1151999-08-31031 August 1999
Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006
ML20211G1221999-08-27027 August 1999
Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d)
ML20211G1831999-08-27027 August 1999
Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS
ML20211F8731999-08-25025 August 1999
Forwards Insp Repts 50-373/99-13 & 50-374/99-13 on 990804-06 & 09-11.No Violations Noted.Fire Protection Program Strengths Includes Low Number of Fire Protection Impairments & Excellent Control of Transient Combustibles
ML20210U3201999-08-17017 August 1999
Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted
ML20210N5651999-08-0606 August 1999
Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes
ML20210M9131999-08-0202 August 1999
Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed
ML17191B4031999-07-23023 July 1999
Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE
05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999
Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed
ML20210E0501999-07-22022 July 1999
Submits Summary of 990630 Management Meeting Re Licensee Performance Activities Since Start Up of Unit 2.List of Attendees & Matl Used in Presentation Enclosed
ML20210B7071999-07-16016 July 1999
Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7)
ML17191B3951999-07-15015 July 1999
Forwards Environ Assessment & Finding of No Significant Impact Related to Proposed Exemptions for Braidwood,Byron, Dresden,Lasalle & Quad Cities Stations.Proposed Exemptions Would Provide Relief from Requirements of 10CFR50.71(e)(4)
ML20209H5171999-07-15015 July 1999
Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at LaSalle County Nuclear Generating Station for Weeks of 990913,1018 & 1129
ML20209G4031999-07-14014 July 1999
Forwards Insp Repts 50-373/99-11 & 50-374/99-11 on 990614-18.No Violations Noted
ML20209E1211999-07-14014 July 1999
Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram
ML20209F6931999-07-13013 July 1999
Forwards Insp Repts 50-373/99-04 & 50-374/99-04 on 990513-0622.No Violations Noted.Determined That Multiple Challenges to Main Control Room Operators Occurred During Insp Period Due to Human Performance Weaknesses
ML20209G3901999-07-0909 July 1999
Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50
ML20209E0341999-07-0909 July 1999
Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101
ML20210C1521999-07-0909 July 1999
Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage
ML20209E0361999-07-0808 July 1999
Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501
ML20196J9061999-07-0101 July 1999
Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21
ML20196J9131999-07-0101 July 1999
Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3)
ML20209B8241999-06-30030 June 1999
Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes
ML20196J4711999-06-30030 June 1999
Discusses Closure of GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Units 1 & 2
ML20212J0311999-06-21021 June 1999
Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8
ML20196B1951999-06-18018 June 1999
Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated
ML20195J7761999-06-15015 June 1999
Submits Request Relief CR-23,requesting Relief from Code Required Selection & Examinations of Noted Integral Attachments & Proposes to Utilize Alternative Selection & Examination Requirements Similar to Code Case N-509
ML20196G8021999-06-15015 June 1999
Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls
ML20195G7101999-06-11011 June 1999
Informs That Effective 990514,GH Mccallum,License SOP-31412, No Longer Requires Use of NRC License for LaSalle Station. License Should Be Terminated
1999-09-08
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D3191999-10-12012 October 1999
Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon
ML20217A7601999-10-0606 October 1999
Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy
ML20212M0931999-10-0404 October 1999
Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff
ML20217A6201999-09-30030 September 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl
ML20212E7171999-09-22022 September 1999
Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads
ML20212C0591999-09-17017 September 1999
Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97
ML20212A3581999-09-13013 September 1999
Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr
ML20212A1141999-09-10010 September 1999
Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage
ML20211P2211999-09-0808 September 1999
Forwards Insp Repts 50-373/99-14 & 50-374/99-14 on 990809- 13.No Violations Noted.Insp Concluded That Emergency Preparedness Program Maintained in Good State of Operational Readiness
ML20212A8571999-09-0707 September 1999
Informs That Proprietary Document, Power Uprate SAR for LaSalle County Station,Units 1 & 2, Rev 2,Class III, NEDC-32701P,submitted in ,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20211Q6861999-09-0606 September 1999
Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant License Applicants During Wks of 001113 & 20. Validation of Exam Will Occur at Station During Wk of 001023
ML20211F8731999-08-25025 August 1999
Forwards Insp Repts 50-373/99-13 & 50-374/99-13 on 990804-06 & 09-11.No Violations Noted.Fire Protection Program Strengths Includes Low Number of Fire Protection Impairments & Excellent Control of Transient Combustibles
ML20210U3201999-08-17017 August 1999
Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted
ML17191B4031999-07-23023 July 1999
Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE
ML20210E0501999-07-22022 July 1999
Submits Summary of 990630 Management Meeting Re Licensee Performance Activities Since Start Up of Unit 2.List of Attendees & Matl Used in Presentation Enclosed
ML20210B7071999-07-16016 July 1999
Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7)
ML20209H5171999-07-15015 July 1999
Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at LaSalle County Nuclear Generating Station for Weeks of 990913,1018 & 1129
ML17191B3951999-07-15015 July 1999
Forwards Environ Assessment & Finding of No Significant Impact Related to Proposed Exemptions for Braidwood,Byron, Dresden,Lasalle & Quad Cities Stations.Proposed Exemptions Would Provide Relief from Requirements of 10CFR50.71(e)(4)
ML20209G4031999-07-14014 July 1999
Forwards Insp Repts 50-373/99-11 & 50-374/99-11 on 990614-18.No Violations Noted
ML20209F6931999-07-13013 July 1999
Forwards Insp Repts 50-373/99-04 & 50-374/99-04 on 990513-0622.No Violations Noted.Determined That Multiple Challenges to Main Control Room Operators Occurred During Insp Period Due to Human Performance Weaknesses
ML20196J4711999-06-30030 June 1999
Discusses Closure of GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Units 1 & 2
ML20195B6031999-05-24024 May 1999
Ack Receipt of Which Transmitted Changes Identified as Rev 60 to LaSalle Nuclear Station Security Plan,Submitted Per Provisions of 10CFR50.54(p)
ML20206T0081999-05-19019 May 1999
Forwards Insp Repts 50-373/99-03 & 50-374/99-03 on 990401-0512.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations.One Violation Re Two Operators Failure to Log Suppression Pool Temp as Required
ML20206U3641999-05-19019 May 1999
Confirms Plans to Conduct Routine Mgt Meeting on 990630 in Lisle,Il Re Recent Plant Performance & Lessons Learned from Unit 2 Restart
ML20206S5291999-05-14014 May 1999
Forwards Insp Repts 50-373/99-10 & 50-374/99-10 on 990419-23.Violation Noted:Nrc Determined That Previously Unresolved Item Involving Failure to Adequately Implement fitness-for-duty program,non-cited Violation
ML20206G7511999-05-0303 May 1999
Forwards Insp Repts 50-373/99-09 & 50-374/99-09 on 990406-09.No Violations Were Identified.Insp Focused on Actions Recently Taken to Identify Common Causes for Previously Identified Programmatic Radiation Staff Problems
ML20206G6631999-05-0303 May 1999
Forwards Insp Repts 50-373/99-07 & 50-374/99-07 on 990329- 0402.NRC Determined That Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
ML20206K7401999-05-0303 May 1999
Informs That as Result of April 1999 Senior Mgt Meeting, LaSalle Identified as Routine Oversight Plant.Summary of NRC Discussion Related to LaSalle Listed.Meeting Scheduled for 990506 to Discuss Latest Meeting of NRC Senior Managers
ML20205S8101999-04-20020 April 1999
Forwards Insp Repts 50-373/99-08 & 50-374/99-08 on 990311- 26.No Violations Noted.Overall,Insp Results Indicated That Unit 2 Mods Properly Installed & That Plant Matl Condition of Unit 2 Acceptable
ML20205R5461999-04-16016 April 1999
Forwards Insp Repts 50-373/99-02 & 50-374/99-02 on 990217- 0331.Non-cited Violation Re Failure of Operator to Follow Procedure Which Resulted in Surveillance Procedure Acceptance Criteria Being Evaluated
ML20205R4171999-04-16016 April 1999
Forwards Summary of 990406 Meeting Re Readiness for Restart of Plant,Unit 2 & Dual Unit Operation & Recent Plant Performance Review Issued by NRC
ML20205J2381999-04-0505 April 1999
Submits Summary of 990322 Meeting with Util to Discuss Experiences & Performance of Plant Since Startup of Unit 1 Status of Matl Condition & Unit 2 Outage.Associated Meeting Summary & Handouts Provided by Util Encl
IR 05000373/19980171999-03-29029 March 1999
Discusses Insp Repts 50-373/98-17 & 50-374/98-17 & OI Rept 3-98-015 Completed on 981119 & Forwards Nov.Apparent Deliberate Violation of NRC-required Comed Fitness for Duty Program Noted
ML20205D5801999-03-29029 March 1999
Refers to Insps 50-373/98-17 & 50-374/98-17 & Subsequent OI Investigation 3-98-032 Into Info Reported to NRC by Comed on 980518,that Deliberate Violation of NRC-required FFD Program May Have Occurred at LaSalle & Forwards NOV
ML20205G5411999-03-26026 March 1999
Advises of Completion of Plant Performance Review on 990204 to Develop Integrated Understanding of Safety Performance. Overall Performance at Plant Improved as Discussed.Insp Plan & Plant Issues Matrix Encl
ML20205A6411999-03-25025 March 1999
Refers to Investigation Conducted by OI (Investigations Rept 3-1998-028) to Determine If Employment Discrimination Occurred After Contract Worker Raised Radiation Safety Concerns Re Plant.Synopsis from Subj Rept Encl
ML20205A6211999-03-24024 March 1999
Discusses 990226 Mgt Meeting with Util Re Performance of LaSalle Since Startup of Unit 1,status of Matl Condition of LaSalle & Status of Unit 2 Outage.Associated Meeting Summary & Handout Provided to NRC by Util Encl
ML20204J8411999-03-24024 March 1999
Submits Summary of 990226 Meeting Re Performance of LaSalle Since Startup of Unit 1,status of Matl Condition of LaSalle & Status of Unit 2 Outage.List of Attendees & Matl Used Encl
ML20204J7021999-03-22022 March 1999
Confirms Plans to Conduct Mgt Meeting on 990406 at Mazon Emergency Operations Facility to Discuss Readiness for Restart of Unit 2
ML20204E0751999-03-18018 March 1999
Discusses Review of Rev 6M to Portions of Plant Emergency Plan Site Annex
ML20207J8901999-03-10010 March 1999
Forwards Insp Repts 50-373/99-01 & 50-374/99-01 on 990106- 0216.No Violations Identified.Personnel Errors Occurred During Insp Period.Overall Performance of Plant Personnel Acceptable
ML20203F2541999-02-10010 February 1999
Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function
ML20203C9811999-02-0808 February 1999
Ack Receipt of ,Which Transmitted Changes Identified as Rev 59 to Security Plan.No NRC Approval Required
ML20203A1981999-02-0202 February 1999
Forwards Insp Repts 50-373/98-23 & 50-374/98-23 on 981121-990105.No Cited Violations Identified.Two Equipment Problems Identified During Shutdown for Planned Outage Were Not Effectively Addressed to Preclude Problem Recurrence
ML20198N4531998-12-18018 December 1998
Confirms Plans to Conduct Routine Mgt Meeting on 990119 at Mazon Emergency Operations Facility to Discuss Lasalle,Unit 1 Performance & Status of Lasalle,Unit 2 Restart Activities
ML20198E9281998-12-17017 December 1998
Forwards Insp Repts 50-373/98-22 & 50-374/98-22 on 981010- 1120.No Violations Noted.Overall Performance of Plant Personnel Was Acceptable
ML20198F2891998-12-16016 December 1998
Forwards Insp Repts 50-373/98-25 & 50-374/98-25 on 981102-06.No Violations Noted.Insp Was Evaluation of Operator Workaround Program
ML20198B3741998-12-14014 December 1998
Forwards SE Accepting one-time Request for Relief from Certain Provisions of Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a for Certain Plant Safety/Relief Valves
ML20197H3561998-12-0404 December 1998
Final Response to FOIA Request for Docments.Records in App a Encl & Will Be Available in PDR
ML20198B1531998-12-0202 December 1998
Forwards Insp Plan for Next 6 Months & Plant Issues Matrix. Info Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite
1999-09-08
[Table view] |
Text
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~ Septemb'er: 13,.1999
,1- Mr. Oliver D. Kingsley,' Pres denti i, Nuclear Generation Group - :i Commonwealth Edison Company Executive Towers West ill 1400 Opus Place, Suite 500' -
7 Downers Grove, IL '60515 '
SUBJECT:
- ANFB CRITICAL POWER CORRELATION TO CO-RESIDENT GE FUEL -
LASALLE COUNTY STATION," UNIT 1 (TAC NO. MA6091)
Dear Mr. Kingsley:
By letter dated July 9,1999, Commonwealth Edison Company (Comed) provided Siemens Power Corporation (SPC) fuel and General Electric (GE) fuel Minimum Critical Power Ratio data for LaSalle County Station, Unit 1, Cycle 9. This data was sent in response to an NRC letter and safety evaluation relating to the SPC licensing topical report EMF-1125(P)(A),
"ANFB [ Advanced Nuclear Fuel for Boiling Water Reactors) Critical Power Correlation Application for Co-Resident Fuel," Supplement 1, Appendix C, dated May 9,1997, in its July 9, 1999, letter, Comed requested written confirmation that the data provided satisfies the condition of the NRC letter. The staff confirms that the data provided does meet Condition 2 as i stated in the [[letter::05000373/LER-1997-012, :on 970410,low-low Setpoint Function of Ms S/R SRVs Have Not Been Tested IAW TS Sr.Caused by Inadequate Procedure.Procedures Revised to Functionally Test LLS Logic & ADS Logic|May 9,1997, letter]]. ;
Sincerely, Original signed by:
l Donna M. Skay, Project Manager, Section 2 Project Directorate ill Q91gog pgg73 Division of Licensing Project Management p PDR Office of Nuclear Reactor Regulation
! Docket Nos. 50-373 and 50-374 cc: See next page --
l L DISTRIBUTION- 1 l; Docket File - OGC, 015B18 '
PDill r/f- M. Leach, Rlll PUBLIC ACRS, T2E26
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l L DOCUMENT NAME: G:\PDill-2\lasalle\mcpttable.itr.wpd - l
- Te receive o copy of this document, ineeste in the laps: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy j OFFICE - PM:LPD3 , 4 t/A:kPl13 6 BC:S8XF C/ SC:LPD3; ( I NAME- DSKAY-QA M dMODRE - JWElWlRL AMINDIDLA DATE 08/S V99 08/h5 /99- 09/ f /99 A0 C"' f;'^^ ,
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S:ptember 13, 1999
' Mr; Oliver D. Kingsley, President Nuclear Generation Group
' Commonwealth Edison Company Executive Towers West til
~ 1400 Opus Place, Suite 500 Downers Grove,IL 60515
SUBJECT:
ANFB CRITICAL POWER CORRELATION TO CO-RESIDENT GE FUEL -
LASALLE COUNTY STATION, UNIT 1 (TAC NO. MA6091)
Dear Mr. Kingsley:
By letter dated July 9,1999, Commonwealth Edison Company (Comed) provided Siemens Power Corporation (SPC) fuel and General Electric (GE) fuel Minimum Critical Power i Ratio data for LaSalle County Station, Unit 1, Cycle 9. This data was sent in response to an I
NRC letter and safety evaluation relating to the SPC licensing topical report EMF-1125(P)(A), j
~ "ANFB [ Advanced Nuclear Fuel for Boiling Water Reactors) Critical Power Correlation j Application for Co-Resident Fuel," Supplement 1, Appendix C, dated May 9,1997. In its July 9, 1999, letter, Comed requested written confirmation that the data provided satisfies the condition of the NRC letter. The staff confirms that the data provided does meet Condition 2 as stated in the [[letter::05000373/LER-1997-012, :on 970410,low-low Setpoint Function of Ms S/R SRVs Have Not Been Tested IAW TS Sr.Caused by Inadequate Procedure.Procedures Revised to Functionally Test LLS Logic & ADS Logic|May 9,1997, letter]].
Sincerely, !
Original signed by:
l Donna M. Skay, Project Manager, Section 2 Project Directorate til Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 cc: See next page DISTRIBUTION Docket File OGC,015B18 PUBLIC ACRS, T2E26 PDill r/f M. Leach, Rlli i
DOCUMENT NAME: G:\PDill-2\lasalle\mcprtable.itr.wpd TA receive e copy of this document, Indicete in the box: *C* = Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE. PM:LPD3 ,. -4 LIA:16PQ3 6 BC:SEMr O/ SC:LPD3r s NAME DSKAY Q)W CMODl%E JWEl%IBL AMfNDIOLA DATE 08/ S W9 08/h> /99 09/ f /99 Au 00.' f 100 1 OFFICIAL RECORD COPY G[q[g /
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. ensas wt
\*****/ September 13, 1999 Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West lli 1400 Opus Place, Suite 500 Downers Grove,IL 60515
SUBJECT:
ANFB CRITICAL POWER CORRELATION TO CO-RESIDENT GE FUEL -
LASALLE COUNTY STATION, UNIT 1 (TAC NO. MA6091)
Dear Mr. Kingsley:
l By letter dated July 9,1999, Commonwealth Edison Company (Comed) provided Siemens Power Corporation (SPC) fuel and General Electric (GE) fuel Minimum Critical Power Ratio data for LaSalle County Station, Unit 1, Cycle 9. This data was sent in response to an NRC letter and safety evaluation relating to the SPC licensing topical report EMF-1125(P)(A),
"ANFB [ Advanced Nuclear Fuel for Boiling Water Reactors) Critical Power Correlation Application for Co-Resident Fuel," Supplement 1, Appendix C, dated May 9,1997, in its July 9, 1999, letter, Comed requested written confirmation that the data provided satisfies the condition of the NRC letter. The staff confirms that the data provided does meet Condition 2 as
! stated in the [[letter::05000373/LER-1997-012, :on 970410,low-low Setpoint Function of Ms S/R SRVs Have Not Been Tested IAW TS Sr.Caused by Inadequate Procedure.Procedures Revised to Functionally Test LLS Logic & ADS Logic|May 9,1997, letter]]. .
Sincerely, l & 1 Donna M. Skay, Project Manager, ection 2 I' Project Directorate lll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 cc: See next page I
l
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i O. Kingsley LaSalle County Station .
- Commonwealth Edison Company Units 1 and 2 cc:
Phillip P. Steptoe, Esquire Document Control Desk-Licensing Sidley and Austin Commonwealth Edison Company One First National Plaza 1400 Opus Place, Suite 400 Chicago, Illinois 60603 Downers Grove, Illinois 60515 l
Assistant Attorney General Commonwealth Edison Company 100 W. Randolph St. Suite 12 Site Vice President - LaSalle -
Chicago, Illinois 60601 2601 N. 21st Road l Marseilles, Illinois 61341-9757 l U.S. NRC-LaSalle Resident Inspectors Office l 2605 N. 21st Road Mr. David Helwig Marseilles, Illinois 61341-9756 Senior Vice President Commonwealth Edison Company Chairman,LaSalle County Board of Supervisors Executive Towers West til LaSalle County Courthouse 1400 Opus Place, Suite 900 Ottawa, Illinois' 61350 Downers Grove, Illinois 60515 Attomey General Mr. Christopher Crane 500 S. Second Street Senior Vice President-Nuclear Operations Springfield, Illinois 62701 Commonwealth Edison Company Executive Towers West lll Chairman, Illinois Commerce Commission 1400 Opus Place, Suite 900 527 E. Capitol Avenue, Leland Building Downers Grove, Illinois 60515 Springfield, Illinois 62706 Mr. R. M. Krich lilinois Department of Nuclear Safety Vice President - Regulatory Services
. Office of Nuclear Facility Safety Commonwealth Edison Company
- 1035 Outer Park Drive Executive Towers West 111 Springfield, Illinois 62704 1400 Opus Place, Suite 500 Downers Grove, Illinois 60515 Regional Administrator U.S. NRC, Region ill Commonwealth Edison Company 801 Warrenville Road Reg. Assurance Supervisor - LaSalle Lisle, Illinois 60532-4351 2601 N. 21st Road Marseilles, Illinois 61341-9757 Commonwealth Edison Company LaSalle Station Manager Me. Pamela B. Stroebel
' 2601 N. 21st Road Senior Vice President and General Counsel l- - Marseilles, Illinois 61341-9757 . Commonwealth Edison Company P.O. Box 767 Robert Cushing, Chief, Public Utilities Division Chicago, Illinois 60690-0767 lilinois Attorney General's Office 100 W. Randolph Street i Chicago, Illinois 60601 l l
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