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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 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 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 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 ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS 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) 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 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) 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 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 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 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 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) 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 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 ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207D2821999-05-27027 May 1999 Requests That Implementation Date for Unit 1 Be Changed Prior to Startup for L1C10 to Allow Best Allocation of Resources to Implement Unit 1 Amend Prior to Startup for Either L1C9 or L1C10.Unit 2 Will Implement Mod IAW Request 1999-09-08
[Table view] Category:NRC TO STATE/LOCAL GOVERNMENT
MONTHYEARML20055C8011990-06-15015 June 1990 Responds to Re Power Oscillation Transient of Mar 1988 at La Salle.Nrc Determined Acceptable long-term Resolutions for Issue to Enhance Safety of BWRs ML20236V7341987-12-0101 December 1987 Partial Response to FOIA Request for Documents.Forwards Documents Listed in App C ML20211C5251987-02-0606 February 1987 Discusses NRC Analysis of Licensing Schedules for Facility, Per Util 870202 Request for NRC Statement to State of Ca. NRC Sept 1981 - Feb 1982 Monthly Repts to Congress Re Licensing Projections for Pending OL Applications Encl ML20197F8291986-04-15015 April 1986 Forwards Population Density Map for Emergency Planning Zone. Map Developed by ORNL by Projecting from 1982 Census Data & Must Be Taken as Estimate.W/O Encl ML20197F0381986-04-15015 April 1986 Forwards Population Density Map for Emergency Planning Zone. Map Developed by ORNL by Projecting from 1982 Census Data & Must Be Taken as Estimate.W/O Encl ML20138B8451986-03-17017 March 1986 Forwards SALP Repts 50-373/85-01 & 50-374/85-01 & Listed Correspondence Between NRC & Util,In Response to . Periodic Meetings Will Be Held to Assess Util Remedies of Deficiencies Noted in Repts.W/O Encls ML20138Q9071985-11-0505 November 1985 Submits Responses to Listed Comments Re Testing Period for Inservice Diesel Generators,Accessibility of Generators to Crossties & Capability of Vital Bus Auto Load Shedding,Per 851018 Telcon ML20062B5531982-07-19019 July 1982 Responds to 820324 Show Cause Petition & 820503 Amend on Behalf of State of Il.Parts of Petition & Amend Pertaining to Unit 1 Denied.Response Deferred for Unit 2.Decision Will Be Issued Upon Completion of Evaluation 1990-06-15
[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 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 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) 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 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 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 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 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 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 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 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 ML20205D6971999-03-29029 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 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 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 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 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 ML20196F7361998-12-0202 December 1998 Informs That Document GE-NEDC-31531P,Suppl 1, ARTS Improvement Analysis for Lscs,Units 1 & 2,Removal of Direct Scram Bypassed Limits, Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20196G4601998-11-27027 November 1998 Forwards FEMA Correspondence, Transmitting FEMA Final Evaluation Rept for 980318 Emergency Preparedness Exercise at LaSalle Nuclear Generating Station 1999-09-08
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4 DISTRIBUTION:
ydL 1 1IS2 See attached page Docket t'os: 5n-373/374 Tyrone C. Fahner, Esquire
- Attorney General State of Illinois 160 t! orth La Salle Street Chicago, Illinois 60601
Dear Mr. Fahner:
This letter is in response to your petition of fiarch ?4,1982 (Petition) and Amendnent dated l'ay 3,1982, on behalf of the State of Illinois. The Petition and the Anendnent have been considered under 10 CFP 2.?06 of the Comission's regulations. For the reasons stated in the enclosed " Director's Decision under 10 CFR 2.206," the parts of the Detition and Anendnent pertainino to La Salle Unit I have been denied. Those portions of the Petition and trendnent pertainino only to La Salle County Station, Unit 2, have been deferred and the !TC uill continue to review these natters. I will issue a decision with renard to those natters as soon as our evaluation is connleted, and in any case prior to a decision regarding an operating license for La Salle Unit 2.
A copy of this decision will be filed with the Secretary for the Comission's review in accordance with 10 CFP. 2.206(c). As provided in 10 CFR 2.206(c), this decision will bccone the final action of the Comission in 25 days, unless the Comission deternines to review the decision within that tire. I also enclose a copy of a notice that is being filed with the Office of the Federal Reqister for noblication.
Sincerely, f
3 Harold R. Denton, Director Office of finclear teactor Regulation
Enclosures:
- 1. Director's Decision
- 2. Federal Reoister Notice cc: See next page NRP 8208040575 820719 HR on PDR ADOCK 05000373 o PDR 7 /82 8/ (KEN \\
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La Salle Mr. Louis 0. De1 George Director of Nuclear Licensing
- Commonwealth Edison Company '
P. O. Box 767 .
Chicago, Illinois 60690 - -
cc: Philip P. Steptoe, Esquire ,
Suite 4200 -
One First National Plaza !
Chicago, Illinois 60603 Dean Hansell, Esquire .
Assistant Attorney General 188 West Randolph Street Suite 2315 Chicago, Illinois 60601 William G. Guldemond, Resident Inspector
.'
- La Salle, NPS, U.S.N.R.C.
P. O. Box 224
- Marseilles, Illinois 61364 .
Chairnan La Salle County Board of Supervisors La Salle County Courthouse Ottawa, Illinois 61350 Attorney General
- 500 South 2nd Street Springfield, Illinois 62701 .
Department of Public Health i Attn: Chief, Division of Nuclear Safety l 535 West Jef ferson
. Springfield, Illinois 62761 The Honorable Tom Corcoran United States House of Representatives Washington, D. C.' 20515 Chairman Illinois Commerce Commission' Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 . ..
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w UNITED STATES OF AMERICA DD-82-9 NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION HAROLD R. DENTON, DIRECTOR In the Matter of )
)
COMMONWEALTH EDIS0N COMPANY ) Docket Nos: 50-373
) 50-374 La Salle County Station )
(La Salle, Units 1 and 2) ) (10 CFR 2.206)
DIRECTOR'S DECISION UNDER 10 C.F.R. 2.206 Attorney General Tyrone C. Fahner, Esquire, on behalf of the State of Illinois, has filed a petition pursuant to 2.206, dated March 24, 1982, and an amendment thereto, dated May 3,1982, requesting institution of a show cause proceeding on Commonwealth Edison Company's, La Salle County Station, Units 1 and 2. The petition and amendment set forth allegations of poor construction. In addition, Ms. Bridget Little Rorem, on behalf of the Illinois Friends of the Earth, Essex, Illinois has also filed a petition, dated April 28, 1982, pursuant to 10 CFR 2.206, requesting institution of show cause proceedings on the basis of certain allegations concerning improper construction practices at the La Salle County Station, Units 1 and 2, and further, sought to halt immediately further loading of nuclear fuel at La Salle Unit 1. Ms. Rorem's petition enclosed four affidavits from construction workers setting forth allegations of various improper practices. The NRC staff denied the petitioners' requests for immediate relief by letters dated April 17,1982, May 19,1982 and June 2,1982. In connection with its review of the Attorney General's petition, the NRC staff met with representatives of Commonwealth Edison Company, Sargent and Lundy, and the Attorney General h>W rr 7otroy'058R
on March 31, 1982, in Bethesda, Maryland. On April 13, 1982, the Attorney General submitted coaments on Commonwealth Edison Company's presentation at the March 31st meeting. Commonwealth Edison Company has responded to the Attorney General's petition in submittals dated March 31, May 7, and May 18, 1982. The Attorney General provided additional comments in a letter dated May 26, 1982.
A license was issued on April 17, 1982 to the Commonwealth Edison Company to permit the loading of nuclear fuel assemblies into La Salle Unit I and also permitting initial criticality and low power physics testing. The April 17, 1982 license authorized power levels up to and including 5 percent of rated power; however, it requires NRC staff approval prior to going beyond zero power testing. Specifically, the license contained a license condition which stated:
"The licensee shall complete its assessment of the rebar damaged due to drilling and coring in concrete and the structural adequacy of the off-gas building roof. The results shall be reported to the NRC staff for review and approval, prior to operation following initial criticality and zero power physics testing."
The NRC staff has completed its special inspection into those allegations identified in the above petitions required in order to proceed with licensing of La Salle, Unit 1. The enclosed Region III special inspection report addresses the HRC findings with respect to these allegations as expanded following interviews held with allegers. As indicated in the report, we have grouped the allegations as expanded into three categories:
(1) Category 1 - those allegations requiring satisfactory resolution in
- order to proceed with the licensing process of La Salle Unit 1; l (2) Category 2 - those allegations that were judged to require a followup on i a longer time frame which relate to only La Salle Unit 2, personnel
- concerns, and activities not having immediate safety impact; and l
l l
(3) Category 3 - those allegaticns which range from the too general and unsubstantiated to pursue to those which are subject to regulatory jurisdiction of other agencies, or for which no further action is required by the NRC staff.
As indicated by the report, there were 20 Category 1 allegations of which some were not able to be substantiated by the NRC investigation.
For several others, the factual allegations were correct; however, these conditions were found to be acceptable when the entire system of controls was examined. One allegation relating to improper site security matters resulted in finding violations of the licensee's security requirements.
When these were brought to the licensee's attention, prompt corrective actions were taken. One allegation of falsification of torque wrench calibration records by a site contractor was substantiated. In a related area, although separate in its cause, a few loose bolts were found on some valves.
To provide greater assurance of the adequacy of the bolt tightness, the license of La Salle Unit 1 is being amended to include a license condition requiring that prior to January 15, 1983, the licensee check the torque on all non-pressure boundary bolts (bolts whose failure will affect the operability of the valve) on each safety-related valve located outside the containment. For non-pressure boundary bolts on safety-related valves located inside containment, a similar program was successfully completed by the licensee prior to the conclusion of this inspection period. For the remainder of the safety-related valve bolting, namely those at the reactor coolant pressure boundary, such a check is not being required on the basis that this bolting has been functionally checked during a preoperational hydro test on the reactor coolant boundary.
f j
.a, The items included in Category 2 concerned matters regarding La Salle -
+
Unit 2 and other matters requiring further NRC attention. These matters arose primarily out of allegations contained in the affidavits submitted to i the NRC and in statements made by persons interviewed by the NRC staff in the course of investigating the allegations. The allegations concern installation activities, a fire, and the condition of the basemat at La Salle Unit 2. The NRC staff will consider these matters further through review of prior inspection reports, additional inspections, and interviews of plant personnel. On the a
basis of this additional review, the NRC staff intends to issue an additional decision prior to taking licensing actions on La Salle Unit 2.
Other Category 2 items included allegations in the affidavits of instal-i lation of damaged equipment, communication problems with representatives of the architect-engineer and poor attitude on the part of management and supervisory personnel. In addition, further assurance that this problem does not exist will be obtained during pre-operational testing, since testing should reveal any problems attributable to damaged or defective equipment. The NRC staff will perform follow-up investigation of allegations directed toward Commonwealth Edison's management and the architect-engineer. On the basis of our review of the allegations, no immediate and substantial safety issue has been identified 1 that would warrant enforcement action or further restrictions of authorized l
power level .
1- The affidavits contain some general allegations of inadequate NRC l
inspection coverage and improper inspector conduct toward plant workers.
t In the absence of a demonstrable link to specific safety problems or' licensee 1
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misconduct, improper conduct or inadequate inspections by NRC inspectors would not warrant initiation of show cause proceedings against the licensee to rectify what would be essentially an internal Commission problem. The NRC staff has thoroughly reviewed and pursued the allegations in the petitions and the affidavits and has not found to date a substantial safety hazard warranting initiation of show cause proceedings.
The NRC staff has included in Category 3 allegations derived from the affidavits and additional statements made by persons interviewed by the NRC for which insufficient information could be developed to warrant further NRC action or for which NRC would not take action. Allegations in the affidavits that piping was improperly installed and that equipment was not installed in 1
accordance with blueprints could not be addressed owing to the lack of specific information that could be developed on the basis of pursuing the allegations with the allegers. During the course of the NRC's investigation of the matters raised in the petitions and affidavits, a general allegation was made that drug and alcohol abuse had occurred at the site, but the alleger was unable to provide any specific information. In view of the lack of specific information and in view of the results of the remainder of the NRC staff's t investigation of the allegations, no further action is contemplated and no 1 basis for enforcement action exists on the basis of the foregoing allegations at this time.
j Allegations were made by the affiants and during further interviews that the circulating water pipe was defective, a bulge existed in the concrete l
l
wall of the condenser pit, and there were loose bolts on beams in the Unit 2 turbine buildings. No further URC action is planned with respect to these allegations because the allegations do not concern safety-related structures ,
and equipment. These matters have been identified to Commonwealth Edison Company for its action as appropriate. Similarly, no further action is contemplated by the NRC with respect to alleged " gross waste" and cost increases that have no apparent bearing on the NRC's health and safety responsibilities. The allegations concerning poor working conditions and inadequate worker safety have been referred to appropriate governmental authorities with jurisdiction over occupational health and safety matters.
It should be noted that neither the Attorney General nor Bridget Little Rorem rely specifically in their petitions on the foregoing aspects of the afff-davits as a basis for initiating show cause proceedings and halting further licensing of the La Salle facilities.
For the reasons set forth in this decision and in my interim responses to the petitioners, the requests of the Attorney General and Bridget Little Rorem for initiation of show cause proceedings have been de_ni_ed_ with respect
, to La Salle Unit 1.
l j In view of the above, I have concluded that for La Salle Unit 1 the public health and safety is not jeopardized, and does not warrant issuance of an order to show cause. However, for La Salle Unit 2, further investigations will be j performed with respect to those outstanding allegations pertaining only to La Salle Unit 2, and the HRC staff will continue to review these matters and issue a further decision prior to taking licensing actions on Unit 2. As provided I
K T
in 10 CFR 2.206(c), a copy of this decision will be filed with the Secretary for the Commission's review in accordance with 10 CFR 2.206(c). , .
'8l Harold R. Denton, Director Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 19th day of July 1982
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9 v
7590-01 -
UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-373 AND 50-374 COMMONWEALTH EDISON COMPANY
-)
LA SALLE COUNTY STATION, UNITS 1 AND 2 -
ISSUANCE OF DIRECTOR'S DECISION UNDER 10 CFR 2.206 Notice is hereby given that the Director, Office of Nuclear Reactor Regulation, has denied .the petitions and amendment under 10 CFR 2.206 filed by the Attorney General of Illinois and Illinois Friends of the Earth for La Salle County Station, Unit 1. With respect to La Salle County Station, Unit 2, the Director has indicated further investigations. A supplemental decision must be made with respect to those allegations pertaining only to Unit 2.
The two petitions addressed numerous allegations of poor construction, falsification of records, inadequate quality control, etc. These allegations were categorized into three categories; whereby the NRC staff concluded that only Category 1 allegations required resolution to proceed with the La Salle Unit 1 licensing process. For La Salle Unit 2, the Category 2 allegations were deferred and the NRC will continue to investigate these matters for a decision in the reasonably near future. Category 3 allegations are those not under NRC jurisdiction or are too general to pursue and no further action i
is required by the NRC staff.
The reasons for the above conclusions are fully described in a " Director's Decision Under 10 CFR 2.206," which is available for public inspection .in the Commission's Public Document Room located at 1717 H Street, N.W., Washington, D.C.
20555, and at the Public Library of Illinois Valley Community College, Rural Route No.1, Oglesby, Illinois 61348. A copy of the decision will be filed with
7590-01 t,
2-
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the Secretary for the Comission's. review in accordance wit'h 10 CFR 2.206(c). . .
Dated at Bethesda, Maryland this 19th day of July 1982.
- FOR THE NUCLEAR REGULATORY COMMISSION
/ AW Harold R. Denton, Director Office of Nuclear Reactor Regulation 9
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,..a DISTRIB UTION: (GREEN TICKET #11706 - 2.206 PETITION DENIAL)
Document Control (50-373) w/ incoming :.,c NRC PDR w/ incoming L PDR w/ incoming NSIC w/ incoming PRC w/ incoming LB#2 Reading ASchwencer ABournia EHyl ton HDenton/ECase CWoodhead, OELD RHoefling, OELD CMiles, OPA SCavanaugh (EDO# 11706)
MBridgers (ED0# 11706)
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PPAS SHHanauer RJMattson RHVollmer RSCheck BJSnyder LBickwit Blue Bag w/ incoming JMurray, OELD Blue Bag w/ incoming AShepard, DRR (3) Blue Bag w/ incoming Y