Letter Sequence Other |
---|
|
|
MONTHYEARML20056G3571993-08-20020 August 1993 Application for Amends to Licenses NPF-11 & NPF-18,deleting TS 3/4.6.1.5, Primary Containment Structural Integrity & Adding TS Administration Controls Section 6.2.F.6,requiring That ISI Program for Post Tensioning Tendons Be Established Project stage: Request ML20058H6491993-12-0202 December 1993 Requests Addl Info Re TS Change Deleting Section 3/4.6.1.5, Primary Containment Structural Integrity, for Plant Units 1 & 2 Project stage: Other 1993-12-02
[Table View] |
|
---|
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: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
[Table view] |
Text
F D cOnA~ W f " % jo,,
o UNITED STATES 8 -
n NUCLEAR REGULATORY COMMISSION
$ 7
$ WASHINGTON, D. C. 20555
%, December 2, 1993 Docket Nos. 50-373 and 50-374 Mr. D. L. Farrar Manager, Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III, Suite 500 1400 OPUS Place Downers Grove, Illinois 60515
Dear Mr. Farrar:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGE DELETING SECTION 3/4.6.1.5, " PRIMARY CONTAINMENT STRUCTURAL INTEGRITY" FOR LASALLE COUNTY STATION, UNITS 1 AND 2 (TAC NOS.
i M87305 AND M87306)
By letter dated August 20, 1993, Commonwealth Edison Company (Ceco) submitted
- a request to amend Facility Operating Licenses NPF-ll and NPF-18, Appendix A, Technical Specifications to delete Section 3/4.6.1.5, " Primary Containment
- Structural Integrity." Based on a preliminary review of your submittal, the staff is requesting the following additional information to support completion of our review:
A. In Attachment A of your submittal under " Description of the Need for Amending the Technical Specifications," it is indicated that in spite of the fact that the Inservice Inspections (ISIS) of the two units were performed 4.5 years apart (in contrast to the 2 year interval stipulated in Regulatory Guide (RG) 1.35, Revision 3) the two units can still be considered as twin units and the surveillances can be performed on an alternate basis. The rationale for the exception as given is the demonstrated tendon integrity during the past ISIS of the two units.
Your submittal does not contain specific data to support this conclusion. The staff is requesting the following information to support our review:
- 1. The data collected at the time of the ISI test (ISIT) for each unit as required by RG 1.18. This data should be presented either in graphs or tabular form.
- 2. The data accumulated from ISIS performed 1, 3, 5,10, and 15 years after the ISIT for Unit I and I, 3, and 5 years after the ISIT for !
Unit 2, as required by RG 1.35, Revision 3. Particular emphasis should be placed on the tendon lift-off force for each of the fixed i tendons; or in the case of random samples for a group of tendons, to the representative lift-off force for the group. In order to determine the trend in the reduction of tendon force, the lift-off 0600h -
9312130166 931202 PDR ADOCK 05000373 3 0i p PDR c
r
.Mr. D. L. Farrar December 2, 1993 force for each group of tendons obtained from the past ISITs should be plotted in the same manner as indicated in RG 1.35, Revision 3. j
- 3. Any other information which might affect the integrity of the tendons as specified in RG 1.35. For example, the effect of high t temperature on relaxation of tendons.
B. Also;in Attachment A under " Description of the Need for Amending the :
Technical Specifications," you state that specification 3/4.6.1.5 is '
redundant to specification 3/4.6.1.1. The staff does not believe that to be the case. Containment integrity is comprised of two components:
leaktight integrity and structural integrity. Structural integrity is a necessary condition of containment integrity but is not sufficient without leaktight integrity. Specification 3/4.6.1.1 deals with leaktight integrity and specification 3/4.6.1.5 deals with structural -
integrity. In view of this fact, your statement regarding the '
redundancy of these two specifications is incorrect and the statement should be changed accordingly. i We request that the response to this request for additional information be provided within 30 days from receipt of this letter. If you have any questions regarding this request, please call the NRC Project Manager, Anthony T. Gody, Jr., at (301) 504-1387.
The reporting and/or recordkeeping requirements contained in this letter affect 1 fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, i i
%n?J Signed gy:
Anthony T. Gody, Jr., Project Manager ;
Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation cc: see next page DISTRIBUTION: Docket File (50-373 & 50-374) NRC & Local PDRs PDIII-2 r/f J. Roe J. Zwolinski J. Dyer C. Moore A. Gody, Jr. 0GC ACRS (10)
B. Clayton RIII C. Tan 0FC b;PDlII-2 PM:PDIII-2 D:PDIII-2 NAME N0YEh AGODYJR A _ JDYER b !
DATE O/M/93 9 /w /93 /2-/ 2 /93 / /93 / /93 / /93 l COPY (YES)/NO @/NO YES/8 YES/N0 YES/N0 YES/NO
l
.. l I
Mr. D. L. Farrar LaSalle County Station Commonwealth Edison Company Unit Nos. I and 2 )
CC: !
Phillip P. Steptoe, Esquire Robert Cushing l Sidley and Austin Chief, Public Utilities Division '
One First National Plaza Illinois Attorney General's Office Chicago, Illinois 60603 100 West Randolph Street '
Chicago, Illinois 60601 ;
Assistant Attorney General 100 West Randolph Street Michael I. Miller, Esquire Suite 12 Sidley and Austin Chicago, Illinois 60601 One First National Plaza Chicago, Illinois 60690 Resident Inspector /LaSalle, NPS U. S. Nuclear Regulatory Commission Rural Route No. 1 LaSalle Station Manager P. O. Box 224 LaSalle County Station 1
~
Marseilles, Illinois 61341 Rural Route 1 P. O. Box 220 Chairman Marseilles, Illinois 61341 LaSalle County Board of Supervisors !
LaSalle County Courthouse Ottawa, Illinois 61350 Attorney General I 500 South 2nd Street Springfield, Illinois 62701 Chairman Illinois Commerce Commission Leland Building :
527 East Capitol Avenue Springfield, Illinois 62706 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Commission ,
799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 Robert Neuman Office of Public Counsel State of Illinois Center '
100 W. Randolph Suite 11-300 i Chicago, Illinois 60601 l I
1
_ ~
I Mr. D. L. farrar December 2, 1993 force for each group of tendons obtained from the past ISITs should )
be plotted in the same manner as indicated in RG 1.35, Revision 3.
- 3. Any other information which might affect the integrity of the i tendons as specified in RG 1.35. For example, the effect of higt(
temperature on relaxation of tendons. ;
B. Also; in Attachment A under " Description of the Need for Amending the !
Technical Specifications," you state that specification 3/4.6.1.5 is ,
redundant to specification 3/4.6 l.1. The staff does not believe that i to be the case. Containment integrity is comprised of two components:
leaktight integrity and structural integrity. Structural integrity is a necessary condition of containment integrity but is not sufficient without leaktight integrity. Specification 3/4.6.1.1 deals with leaktight integrity and specification 3/4.6.1.5 deals with structural '
integrity. In view of this fact, your statement regarding the :
redundancy of these two specifications is incorrect and the statement ,
should be changed accordingly. l We request that the response to this request for additional information be l provided within 30 days from receipt of this letter. If you have any questions regarding this request, please call the NRC Project Manager, Anthony T. Gody, Jr., at (301) 504-1387. ,
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511. .
.1 Sincerely, ;
OlghalSicnod g y ;
Anthony T. Gody, Jr., Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV/V ,
Office of Nuclear Reactor Regulation cc: see next page >
DISTRIBUTION: Docket File (50-373 & 50-374) NRC & Local PDRs PDIII-2 r/f J. Roe J. Zwolinski J. Dyer ,
C. Moore A. Gody, Jr. 0GC ACRS (10) ;
B. Clayton RIII C. Tan i 0FC iAODlII-2 PM:PDIII-2 D:PDIII-2 ;
NAME NOTEh AGODYJR A JDYER b l DATE N/[/93 0 /w /9h G/'L/93 / /93 / /93 / /93 COPY l (YES/N0 6E3/N0 YES/'tF YES/NO YES/NO YES/NO a