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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) ML20217M2871999-10-21021 October 1999 Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased SVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999 Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630 ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217J4411999-10-18018 October 1999 Forwards Exemption from Certain Requirements of 10CFR73.55 for Zion Nuclear Power Station,Units 1 & 2 in Response to Application Dtd 990730,to Allow Util to Discontinue Specific Aspects of Security Plan & SER 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 ML20217G9791999-10-14014 October 1999 Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2 ML20217K7011999-10-13013 October 1999 Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl 05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999 Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action 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 ML20217F7891999-10-0808 October 1999 Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV ML20217F6321999-10-0707 October 1999 Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990721- 0908.No Violations 05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999 Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee 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 ML20212K9421999-10-0505 October 1999 Informs That NRC Accepts 990513 Inservice Inspection Relief Request CR-31 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20217B6351999-10-0505 October 1999 Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in ML20212L1791999-10-0505 October 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2 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 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 ML20217B2991999-10-0101 October 1999 Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry ML20212J6751999-09-30030 September 1999 Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts 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 ML20217A5821999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A9311999-09-29029 September 1999 Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem ML20216G9541999-09-27027 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re 990730 Application for Exemption.Exemption Would Allow Zion Nuclear Power Station to Discontinue Specific Aspects of Security Plan ML20216H4301999-09-23023 September 1999 Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108 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 SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999 Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage ML20212J0451999-09-21021 September 1999 Forwards Safety Evaluation of Licensee USI A-46 Program at Quad Cities Nuclear Power Station,Units 1 & 2,established in Response to GL 87-02 Through 10CFR50.54(f) Ltr ML20212D8231999-09-20020 September 1999 Informs That Effectieve 991101,NRC Region III Will Be Conducting Safety System Design & Performance Capability Pilot Insp at Quad Cities Nuclear Power Station.Insp Will Be Performed IAW NRC Pilot Insp Procedure 71111-21 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 ML20216F8051999-09-17017 September 1999 Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified ML20216F7441999-09-17017 September 1999 Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424 A99025, Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station1999-09-15015 September 1999 Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station ML20212C6961999-09-15015 September 1999 Forwards Insp Repts 50-254/99-17 & 50-265/99-17 on 990823- 0827.No Violations Noted SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999 Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys 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 ML20212A6991999-09-10010 September 1999 Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2 ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20211Q7961999-09-0909 September 1999 Forwards Correction to Administrative Error on Page 8 of NRC Insp Repts 50-254/99-16 & 50-265/99-16,transmitted by Ltr, ML20211Q6511999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Quad Cities Operator License Applicants During Wk of 000327.Validation of Exam Will Occur at Station During Wk of 000306 ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P6171999-10-21021 October 1999 Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4) SVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999 Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630 ML20217M4361999-10-19019 October 1999 Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl 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 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 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 ML20217K7011999-10-13013 October 1999 Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl 05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999 Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action 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 05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999 Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee 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 SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999 Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage 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 A99025, Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station1999-09-15015 September 1999 Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999 Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring ML20211Q9011999-09-0808 September 1999 Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed 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 ML20211J0311999-08-30030 August 1999 Agrees with Content in NRC 990810 Memo Re Plant Spent Fuel Pool.Memo Contains Accurate Summation of Info That Util Communicated to NRC During 990713 Telcon 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) ML20211G8191999-08-26026 August 1999 Forwards Amend 6 to Fire Protection Rept for Zion Nuclear Power Station,Units 1 & 2, IAW 10CFR50.71(e).Attachment 1 Contains Summary of Changes SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-08-13013 August 1999 Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety SVP-99-147, Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl1999-08-13013 August 1999 Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999 Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2 SVP-99-154, Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated1999-08-13013 August 1999 Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999 Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station 05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999 Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999 Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210K0771999-07-30030 July 1999 Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46 ML20210J0861999-07-30030 July 1999 Requests NRC Approval of Exemption from Certain Requirements of 10CFR73, Physical Protection of Plants & Matls, by 990921.Exemption Is Needed to Support Scheduled 991001 Implementation of Plant Sf Ni.Encl Withheld,Per 10CFR73.21 05000254/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed1999-07-29029 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed ML20210J8951999-07-29029 July 1999 Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999 Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr SVP-99-151, Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 21999-07-23023 July 1999 Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-150, Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept1999-07-23023 July 1999 Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept 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 ML20210E2151999-07-23023 July 1999 Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition ML20216D3781999-07-21021 July 1999 Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA SVP-99-146, Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 9906251999-07-21021 July 1999 Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 990625 ML20210D2961999-07-20020 July 1999 Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761 ML20216D7061999-07-19019 July 1999 Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21 ML20210C2561999-07-19019 July 1999 Forwards Rev 1 to Calculation 22S-B-110X-0068, Determination of Heat Load for Assemblies F50D & Z33A, as Replacement Pages to Rev 0.Calculation Submitted Re Request for Approval of Proposed Plant Defueled Station EP ML20209H2991999-07-16016 July 1999 Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999 Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7 1999-09-08
[Table view] Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML19325E9801989-11-0101 November 1989 Requests That Author Name Be Placed on Distribution List Re Schedule of Hearing in Alchemie Case.W/Certificate of Svc. Served on 891101 ML19324C0611989-08-27027 August 1989 Ack Receipt of Response to Senator Harkin Re Author Ltr About Containment Sys at Plant.Nrc Taking Too Long to Mandate Changes at Plant ML20247F8061989-07-0505 July 1989 FOIA Request for Documentation Re Incidents of Drug &/Or Alcohol Abuse During Past Five Yrs Amoung Employees or Contractors ML20247E6951989-06-27027 June 1989 Advises That Newly Formed Environ Conservation Organization Intends to Oppose Any Util Actions That Might Impact Negatively on Future Operability of Facility ML20247H3631989-06-26026 June 1989 Advises of Formation of Resources Conservation Organization. New Group Intends to Oppose Any Util Actions That Might Impact Negatively on Future Facility Operability.Ad Rossin Will Serve as Organization Coordinator ML20245B3981989-05-0808 May 1989 Discusses Technical & Safety Concerns Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels at Plant ML20248H5801989-03-28028 March 1989 Advises That Plant Evacuation Time Estimates within Plume Exposure Pathway EPZ for Plant Consistent w/NUREG-0654,App a ML20245B4081989-03-10010 March 1989 Requests Response to 881014 & 890119 & 23 Ltrs Re Technical & Safety Concerns at Plant ML20244B0011989-03-0808 March 1989 Lists Facts to Consider for Action to Fix or Close GE Reactors Once & for All ML20245B4091989-01-23023 January 1989 Refers to Re Corrosion Inhibitors in Closed Water Sys at Plant.Last Sentence on First Page of Ltr Should Be Changed to Read One Example Is Loss of Air Cooling to Shutdown Board Rooms at Sequoyah ML20245B4101989-01-19019 January 1989 Requests That Jg Partlow Pursue Completion of Engineering Assignment of ED Buggs at Plant Concerning Corrosion Inhibitors for Closed Water Sys.Draft Engineering Rept Recommending Corrosion Inhibitors for Closed Water Sys Encl ML20206D8951988-10-15015 October 1988 Expresses Opinion That Plants Should Remain Closed Until Converted to Alternative Fuel Source ML20245B4121988-10-14014 October 1988 Informs of Several Technical Concerns Expressed While at Util & Requests That Jg Partlow Pursue Resolution of Listed Concerns ML20204J3211988-09-29029 September 1988 Identifies Several Deficiencies Re Guidance in NUREG-0654. No Traffic Control Plans Provided & Location & Extent of Congestion Not Indicated.Time Estimate Study Does Not Indicate Number of Vehicles Needed for One Trip ML20206D9711988-09-0808 September 1988 Forwards Ltrs Exchanged Between NRC & Author in 1984 Re Problems in Commercial Nuclear Power Field & Change in Federal Regulations to Allow Senior Reactor Operator to Deviate from Tech Specs in Emergency ML20206D9451988-08-12012 August 1988 Annotated Ltr Expressing Appreciation for Reply to & Assurance in Response to Concerns Pertaining to Operation of Ref Plants ML20245D6611988-08-0808 August 1988 Submits Listed Comments in Response to Re Safety Practice to Schedule Nuclear Plant Operating & Maint Personnel for 16 H Shifts &/Or Excessive Overtime ML20206E0281988-07-0707 July 1988 Advises That Nuclear Industry Overlooked Most Important Lesson Resulting from TMI Accident,To Wit,That Station Operator/Mgt Official Stationed in Control Room Would Have Prevented Accident ML20151X9371988-07-0101 July 1988 FOIA Request for Le Phillips 880407 Memo to Ma Ring ML20150A7961988-06-30030 June 1988 Comments on Util 880616 Request to Suspend Antitrust License Condition.Economic Advantages for Util Owning Nuclear Power Plants Have Failed to Materialize ML20205C1191988-06-16016 June 1988 FOIA Request for Listed Documents Re QC Inspector Reinsp Program ML20155B6651988-06-16016 June 1988 FOIA Request for plant-specific Documents Re Fire Protection Requirements,Insp repts,hardware-specific Deficiencies & NRC Communications W/Util ML20206E0361988-04-29029 April 1988 Opines That 10CFR50.54(x) & (Y) Superfluous & Dangerous.Nrc Should Instruct Operators Not to Depart from Tech Specs in Emergency.Author Resume Detailing Experience in Commercial Nuclear Power Field Encl ML20207B1031988-04-18018 April 1988 Urges Cancellation of Paragraphs X & Y of 10CFR50.54 Re Tech Specs & Policy for Operating Nuclear Plants, Respectively ML20155A7431988-02-24024 February 1988 Discusses Safety Problems at Comm Ed Nuclear Power Plants Re Risking Fuel Meltdown by Turning Off Safety Sys as Directed by Util Policy in Emergency If Core Cooling Is Adequate. Vice President Instruction Encl ML20148G9001988-02-0101 February 1988 FOIA Request for Documents Re 10CFR50,App R Insps & Enforcements ML20206E0431988-01-29029 January 1988 Expresses Concern Re Two Hazardous Practices at Ref Plants, Including Risking Meltdown by Authorizing Operators to Turn Off Nuclear Plant Safety Sys During Emergency ML20149G1051987-12-18018 December 1987 Opposes NRC Reduction at TMI-2.Reducing Staff Prior to Completion of Core Removal Inappropriate & Misguided Move. Recent Shutdown of Oyster Creek for Incident Re Destruction of Data Decreases Util Standing W/Local Residents ML17303A6161987-09-30030 September 1987 Forwards Scenario Review for Rancho Seco Emergency Preparedness Exercise,871104. Incomplete Scenario Provided for Review.Plant data,in-plant Chemistry & Radiological Data & Controller Info to Support Fire Drill Missing Elements ML20235T7341987-09-0101 September 1987 Requests That EIS Documents Re Meltdown Prepared by Impartial Sources Be Made Available to Public.Observation of Plant Life Indicates Level of Contamination of General Environ Causing Widespread Severe Damage ML20238B7731987-08-0707 August 1987 FOIA Request for Records Explaining Status of Listed LERs Omitted from List,Previously Received from Nrc,Of LERs Filed by Commercial Nuclear Power Plant Licensees for Operating Year 1986 ML20236E6951987-07-20020 July 1987 Forwards Corrected Certificate of Svc of Appeal from Licensing Board Denial of Motion to Reopen Record Filed on 870720.Certificate Filed W/Appeal Mistakenly Read 870620. Correct Date of 870717 Reflected in Encl Certificate of Svc ML20238E0261987-07-15015 July 1987 Responds to Recipient 870528 Response to Bg Strout Re Maine Yankee & Pilgrim.Author Distressed by NRC Answers & Requests Addl Response to Listed Questions ML20235L7061987-07-0808 July 1987 Opposes Util Application for Amends to Licenses,Allowing New Ownership & Financing Arrangement.Nshc Should Not Be Made W/O Public Hearings on Serious Financial Qualifications Questions ML20235K0421987-07-0202 July 1987 FOIA Request for List of All Licensed Reactor Operators & Senior Reactor Operators for Facilities ML20235F7451987-06-30030 June 1987 FOIA Request for Documents Re Safeteam Programs Being Used at Listed Facilities ML20215L4871987-06-23023 June 1987 Urges NRC Not to Approve Comm Ed Request for Amend of Any OL Re Braidwood 1 & 2 & Not to Determine No Significant Hazard Exists W/O First Holding Adjudicatory Hearings on Serious Financial Qualifications Issues ML20215L5051987-06-23023 June 1987 Provides Brief Updated Rept on Status of Comm Ed Proposal Before State of Il Commerce Commission to Restructure Ownership & Other Financial Arrangements Re Facilities.Urges NRC Not to Make Finding Prior to Hearing ML20215D6371987-06-12012 June 1987 Forwards Reply to Responses from NRC & B&W Owners Group. NRC Response Evidences No Independent Review of B&W Claims. Commission Urged to Take Personal Jurisdiction of Petition to Ensure That Latest Commitment Not Frustrated ML20235P2801987-06-0606 June 1987 Appeals Initial FOIA Decision.Exam of Listed Encl marked-up Matl Requested.Author Will Continue Fight to Release Documents Re Work as Investigator in Apr & May 1977 ML20236H1481987-05-30030 May 1987 Discusses Varga Reply to 870428 Mailgram Re Proof That LOCA Could Not Occur in Reactor Core at Plants.Evidence in Files of Repeated AEC & NRC Repression & Ignorance of Legitimate ACRS Concerns Cited.Congressional Hearings Requested ML20209H0151987-04-29029 April 1987 Urges That NRC Not to Approve Util Request to Amend License NPF-66 or Determine That No Significant Hazards Exist W/O Holding Adjudicatory Hearings on Financial Qualifications Issues Raised by Request to Restructure Facility Ownership ML20215K8391987-04-22022 April 1987 Opposes Licensing of Facilities for All the Same Old Reasons ML20214E2281987-04-16016 April 1987 FOIA Request for PRAs for Listed Plants Be Placed in PDR ML20214L0951987-03-13013 March 1987 Comments on Proposed Rule 10CFR50 Re Mod of Safety Rules to Enable Facilities to Startup Operation.Opposes Rule Due to Result of NRC Abdicating Responsibility as Protector of Safety of Populations Exposed to Radiation During Accidents ML20236D9381987-03-0404 March 1987 Partially Withheld Ltr Discussing Nuclear Power Industry Problems as Encountered During 6 Yrs of Employment at Limerick.Shoreham, & Hope Creek.Demotions & Terminations for Reporting Safety Concerns Described ML20215K8531987-02-24024 February 1987 Advises That Nassau County Board of Cooperative Educational Svcs Has Not Entered Into Any Agreement W/Lilco to Have Salisbury Campus Used for Relocation Facility in Event of Radiological Emergency ML20207T2381987-02-18018 February 1987 FOIA Request for Rept on Odds of Large Radioactive Release at Us Commercial Nuclear Reactors,Including Surry,Peach Bottom,Sequoyah,Grand Gulf & Zion ML20236D1281987-02-15015 February 1987 Forwards Preliminary Investigation of Worker Allegations About Safety of Plant Conducted by Gap in 1986.Investigation Revealed Enough Info to Raise Serious Questions Re Const Quality.Petition Per 2.206 Forthcoming ML20209H4831987-02-0303 February 1987 Forwards Proposed Findings of Fact,Brief of Intervenors, Intervenors Motion for Extension of Page Limit for Brief & Notice of Appearance of Rl Jones 1989-08-27
[Table view] |
Text
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l erares of parties and certain other Ident! 'ylop
(' detalls have been renoved In order to prevent-p a clearly unwarranted Invaston of the pernon:,1 p'r!vacy of the Individuals Involved.
United States Nuclear 3 Regulatory Commission R:gion 111' 799 Roosevelt Road - Box 2027 i '
iGlen Ellen, IL 60137 ATTNs Charles B. Weil, 2nvestigatien and Compliance specialist In reply to your. letter of August 4, 1988,.I have the following comments.
)
The effect that sixteen hour shifts hno on nuclear plant operations in the past is not the issue. and/or excessive My ove Is it a safe practice to schedule nuclear question'was as follows. 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> shifts and/or
-plant? operating.and maintenance personnel for 1In view of the millions
-oxcessive en plant overtime.
~
compliance inspections, it is my opinion that some consid ation should be given to the number of hours plant personnel work.
reaction time I,oss of'or inadequate sleep effects judgement, Frequently people working and the decision making process.
chifts reduce their hours of sleep in order to meet the demands for f their time by their employer, the family, civic and l social have respona.t-difficulty bilities. . To compound these problems many peop e adapting to a constantly changing' sleep schedule dictated by rot chift assignment.
It is.my. opinion that nuclear plant operating and maintenance personnel should not be scheduled for more Further, there shouldthan eight hours pe be sixteen and' forty-eight hours per week.
hours between shift changes.
I am aware that nuclear generating plants are controlled h tby man total automatic fail safe systems and have every safe guard t a can design. However, operators are essigned to assure the systemsIf th operate within prescribed limits. l t the operator must have the knowledge, the judgement and the a e ,
to respond to the emergency.the wrong decision if he has not had adequa as a supervisor--manager I know from first ofhand oil experience and coal thatfired Na l
steam generating plants.
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Other demands ceployees on rotating shif ts have' problems sleeping.for their time problem. I have actually seen people fall asleep while standing up.
' e: emes of parties and certeln $ ot er Identifyin,
[ details have been removed In order to prevent a clearly unwarranted invasion of the persc.n.i arivacy of the tedivid.ints Inve,1ved.
CC: Congressman S. Dennis Hastert CLN/jsh 4
e me.
4
_ _m___-_m.__-._____. - _ _ _ _ _ _ - _ _ _ _ . _ _ . - _ _ , _ _ _
MF.NTS '
-b POlt Y POLIC estended pededs of abundown for parannount eeneidereUonin such erfve ' .mejor mehenense or me)st setborissues.abaB be bt significant plant medincetiens;and p)1be sedocuensla e eDecuveness of oddition of a phrase e Was operatirepemennd wedd be highly estended obvidownpad freesthe
-is to eonside,ese erover.me enlaeL.
in . dwes ore sa anIndividualbeels. encewaged
. ,ersiore si eI.bst so., wedd,WBowlicensed ire t..e
- so, e e,
,,e.e,e es.i.g ,d.ar - d
,,b.,.s.
o,ar. e.,orso d.iu. roe 1,:;feme,drd.m,,d,-
. IAcensus of opereung plants and board delag theh tour of duty.
ePPlicants for operating beenses abal con swatnem seronmation oosriaen '
establish eestrols to pmvent elinesens 34r.84wasee P.Creder.(ars)mst* '
where fatigue sodd moose 6e obtuty of opersuas personnet te keep the master ,ggMeMWM eine asth der
- ' ** *' Jer the N dear Reguletary Cesenteessa.
bin and 6e m pahaA.Ewebend. .
everthne-4ey Jobes ted fossere est Anflance fougue.
The objeceve of 6e sostrels would be Q#*/g A"" 8#
N M*m eum5seriene areasA to assure that,to the estaat practiesble, personnet are not as to sbh J dunes wb!!eina fa e 1 eould algutScancy ese elrmental
.sadison .et siertosas er b!r decislas ,
sepabnity.The sentrois abaB to
. the plant star who perform selsted funcuens (eg, eenler sessaar operetern, peactor operstars, health peysicista,suaR!ary yters,and boy maintenance
- iasperseasel Enoaghpirat operst should be e,mployed to malatela edequele shlrt coverage without restine benvy use of evertime.h objective is tohave operating personne! mark e ocma! shut day.eboer wed w%.e the plantis operating.However.in event that maioreseen problems petelre e F3 SeeN
- smsus em substan6a! amounts of evertime to'be osed er dwing extendedperlede of stueleer Powerplant Statt Wertuis g'
, "g
,g,',I
- modma. - en.te u.e foBowing guidelines ebaB be messetMedser Regulatory a.AnInd cour.;iselas. r,.e.ied ividualobould wo,t om - met.be
.os,e.c ,,bbm.o. ef,evi e,,on.,
seder power plant stag str gcg! g time).
,a,mi,ied t. wo,b more .a. - -
. 0e rei,r.ar, .. .e .n, -bw ,e,io& so, mere .a. .
bours in any #-bow peded mer mese
- pludearRegelseoryComtalasles thaa 72 bows in any sevenday persed pub 1thed a"Pulicy on Facters Censlag (aB enduding ab!ft hrmover ums).
. Fattrue of Opentirig Personnelat s. Abrea of atkast eightbeare Divelear Russes.* 4F FR Fast. should be aDowed between week Comments puerived sinos pub 11ce5em periods (indeding abih turnover thme).
l beve revealed yestions eencerning te d.Except during extended abstdown petity statement Accordingly.the Periods,the nas of overties should be
' gober etateness has been avised and seasidemd on anledividualbasis and G,e resteed werden is reproduced belour. mot for the entre star en a eht, )
OdgesIndmec(11m addidea.of a Recognidagthatvery onesed sentaner whldespUcitly states st &s edicumstances may arine .
e of ne workirq bow policyis devia6an from the above to operogma'personnelwork an 8 such deviation abat be a by how day.e6&ser weele (t)N addissa, the plant manager er his .or ofa se to bdicate that the statgg beer sustrictier.: are applicable higbar hvels or maangement.
1 PS PA 34 em I
.'. unit o siarts
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NUCLEAR RECULATORY COMMISSION
- [. $ cruou m veo moosevett acao tr r ! '
otsu stovw.eLuwoes soist 1
see.*.
DO k M L .
! Docket'No. 50-456;'50-457, 50-454; 50-455, 50-237; 50-249, 50-373; 50-374,.
'50-254; 50-265, 50-295; 50-304 Commonwealth Edison Company ATTN: 'Mr. Cordell Reed
. Senior Vice President Post Office Box 767 Chicago, IL 60690 Gentlemen:
This refers to'the routine safety inspection conducted by Messrs. R. Lerch -
and M. Kunowski of this office from August 16, 1988 to August 2, 1989, of.
activities at the Braidwood, Byron, Dresden, LaSalle, Quad Cities and Zion Nuclear Power Station.-authorized by NRC Operating Licenses No. NPT-72, ho. NPF-77; No. NPF-37, No. NPF-66, No. NPF-19 No. NPF-25; No. NPF-11,
^ No. NPF-18; No. NPF-29, No. NPF-30; No. NPF-39..No. NPF-48, and to the discussion of our findings by telephone with T. Kovach and others of your
. staff-at the conclusion of the inspection.
The enclosed copy of our inspection report identifies areas examined during the inspection. Within these areas. the inspection consisted of a selective examination of procedures and representative records, observations, and
- interviews with personnel.
As a result of this inspection, we are concerned that you do not appear to have sufficient measures in place to' ensure that safety-related work is not being jeopardized by personnel having worked too many hours. In this regard we request that you respond to the concerns identified in Section 4 of this report within 60 days and include'in this response the measures that Commonwealth. Edison has taken or plans to take to ensure consistent application of the overtime requirements at all Commonwealth Edison Nuclear Stations.
'No violations of NRC requirements or deviations from comitments were identified during the course of this inspection.
In accordance with 10 CFR 2.790 of the Comission's regulations, a copy of this letter, the enclosed inspection report and your response will be placed in the NRC Public Document Room.
-- Q b d19- ~
Enclosure Two
u .: .. .
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. Consnonwealth Edison Company 2.g 4 gg We will gladly discuss any questions you have concerning this inspection.
I Sincerely, .
)3abc LMw Edward G. Greenman, Dirdefor Division of Reactor Projects
Enclosure:
Inspection Reports No. 50-456/88024(DRP); 50-457/88024(DRP)
No. 50-454/88015(DRP); 50-455/88014(DRP)
.No. 50-237/88020(DRP);L50-249/88021(DRP)
No. 50-373/88023(DRP); 50-374/88022(DRP)
No. 50-254/88022(DRP); 50-265/88022(DRP) ~
No. 50-295/88017(DRP); 50-304/88017(DRP) cc w/ enclosure:
.T. J. Maiman, Vice President, PWR Operations T. Kovach, Nuclear Licensing Administrator T. Joyce.. Station Manager, Zion R. E. Querio, Station Manager, Braidwood D. E. Cooper, Regulatory Assurance Supervisor J. Eenigenburg, Plant Manager Dresden -
G. J. Diederich Station Manager, LaSalle R. L'. Bax, Plant Manager Quad Cities R. Pleniewiecz, Station Manager, Byron DCD/DCB (RIDS)
Licensing Fee Management Branch Resident Inspector, RIII Braidwood Resident Inspector, RIII Byron Resident Inspector, RIII Dresden Resident Inspector, RIII LaSalle Resident Inspector, RIII Quad Cities Resident Inspector, RIII Zion D. W. Cassel, Jr., Esq.
~ Richard Hubbard J. W. McCaffrey, Chief, Public Utilities Division Diane Chavez, DAARE/ SAFE H. S. Taylor, Quality Assurance Division David Rosenblatt, Governor's Office of Consumer Services Mayor, City of Zion E. Chan, DGC G. Berry, OGC Stephen P. Sands, NRR L. 01shan, NRR, M C. Well, RIII
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4 U.S. NUCLEAR REGULATORY COMMISSION REGION III
^ 7 Report Nos. 50-456/88024(DRP); 50-457/88024(DRP) 50-454/88015(DRP); 50-455/88014(DRP) .
50-237/88020(DRP); 50-249/88021(DRP) 50-373/88023(DRP); 50-374/88022(DRP) 50-254/88022(DRP); 50-265/88022(DRP) 50-295/88017(DRP); 50-304/88017(DRP)
Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 50-454; 50-455' NPF-37; NPF 50-237; 50-249 DPR-19; DPR-25
' 50-373; 50-374 NPF-11; NPF-18 50-254; 50-265 DPR-29; DPR-30 50-295; 50-304 DPR-39; DPR-48 Licensee: Commonwealth Edison Company Post Office Box-767 Chicago,'IL 60690 Facility Name: Braidwood Nuclear Power Station, Units 1 and 2 Byron Nuclear Power Station Units 1 and 2 Dresden Nuclear Generating Station, Units 2 and 3 LaSalle. County Station Units 1 and 2 Quad Cities Nuclear Generating Station, Units 1 and 2 Zion Nuclear Power Station, Units 1 and 2 Inspection At: Region III, Glen Ellyn, Illinois Inspection Conducted: August 16, 1988 to August 2, 1989 Inspectors: R. Lerch M. Kunowski Approved By: D Shafer fef Reactor Projects Branch 1 late e
Inspection Sunnary
-Inspection from August 16, 1988 to August 2. 1989 (Report Nos.
50-45b/88024IDRP); 50-457/88024(DRP) 50-454/88015(DRP); 50-455/88014(DRP) ;
50-237/88020LDRP); 50-249/88021(DRP) 50-373/68023(DRP); 50-374/88022(DRPJ; 50-254/88022LDRP); 50-265/88022(DRP) 50-295/88017(DRP); 50-304/88017(DRPJ Special unannounced inspection by region-based inspectors of Areas Inspected:
procedures and data regarding control of overtime in accordance with the NRC Policy Statement " Nuclear Power Plant Staff Working Hours" and an allegation.
Results: No violations or deviations were identified; however, several concerns were forwarded to the licensee for response.
A'!'l ol( , g
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DETAILS
- 1. Persons Contacted Commonwealth Edison Company (Ceco) -.
- John F. Gudac, Corporate Ma'intenance Superintendent
- Frank Rescek, Assistant Radiation Protection Director
'*Neil P. Smith, BWR_ Licensing Supervisor
- Gerald L. DeYoung.-BWR Licensing Engineer
+* Richard Flessner, PWR Operations
+ Thomas Kovach, Nuclear Licensing Manager
+ Steven'Hunsader. Nuclear Licensing Administrator
+ Charles Sargent, Administrative Engineer
- Denotes those. attending the working meeting conducted on August 19, j 1988, and at other times throughout the inspection period.
+ Denotes those contacted by telephone call on August 2, 1989.
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- 2. Details
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This inspection was conducted to. determine the overtime practices at <
each of the licensee's nuclear sites and whether they meet the " Policy on Factors Causing Fatigue of Operating Personnel at Nuclear Reactors" which was issued in Generic Letter No. 82-12 on June 15, 1982.
The inspectors reviewed the Technical Specifications (TS), procedures and licensee correspondence with the NRC regarding overtime limits. !
Overtime records covering four two-week pay periods at Braidwood, Dresden and LaSalle were reviewed to evaluate the amount of overtime usage.
Byron and Braidwood: Byron and Braidwood are required by Technical Specification 6.2.2.e to develop and implement administrative procedures to limit the working hours of unit staff, such as licensed sen'c.r operators, licensed operators, health physics personnel, equipment operators, and key maintenance personnel, who perform safety-related functions. The amount of overtime worked by unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours as contained in Generic Letter 82-12.
The inspectors determined that Byron and Braidwood have developed administrative procedures to satisfy the technical specifica, tion:
The procedures in place at the time of the inspection were Byron procedure BAP 100-7, (Revision 3, October 15,1986)," Overtime Guidelines for Personnel That Perform Safety Related functions "
and Braidwood procedure BwAP 100-7, (Revision 0, July 26, 1985),
" Overtime Guidelines for Personnel That Perform Safety Related Functions." Discussions with licensee representatives and a review of these procedures indicate that the licensee applies the procedure 2
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only to individuals who perform both safety-related work and who compose the TS required minimum shift complement.
During the time period inspected for Braidwood (56 days) the amount of overtime worked in days of 16' hours,by department, was as follows:
Operations - 316 instances where a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> day was worked.
Maintenance - 174 instances where a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> day was worked Radiological - 150 instances where a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> day was worked 1
The total number of individuals working 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> days was not determined. ]
As indicated in the data where individuals worked consecutive days with i a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> shift per day, it appeared that operations personnel exceeded the'24 in 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit on six occasions. Maintenance personnel. exceeded j the 24 in 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit on three occasions. Radiological / Chemistry personnel exceeded the 24 in 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit on 14 occasions, once with four consecutive 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> days and twice with three consecutive 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> days. The inspectors determined that all licensed operators met the policy but could not determine whether the other individuals were -
performing safety-related work as part of the shift complement to whom the GL 82-12 guidelines are applied or whether appropriate management approval was granted for this overtime.
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LaSalle: LaSalle is required by Technical Specification 6.1.C.7 to develop and implement administrative procedures to limit the working l hours of unit staff, such as, senior reactor operators, reactor operators, health physicists,. auxiliary operators, and key maintenance f j
personnel, who perform safety-related functions. The TS also states J that adequate shift coverage shall be maintained without heavy use of I overtime, but if unforeseen problems occur that require the use of substantial amounts of overtime, overtime shall be used following specified guidelines. The guidelines, specified in the TS, match the NRC policy statement. Deviations from the guidelines shall be authorized by the Production or Services Superintendent or higher g level of manag2 ment. The authorization shall be in accordance with procedures and the basis for the deviation shall be documented. The procedures are also required to include controls such that individual overtime shall be reviewed monthly to assure that excessive hours have
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not been assigned. Routine deviations from the hour guidelines in the TS are not allowed.
The inspectors determined that LaSalle has devel'oped administrative procedure LAP-100-17 (Revision 5. January 25,1988)," Overtime Guidelines for Personnel that Perform Safety Related Functions,"
to satisfy the TS. Discussions with licensee representatives, a review of the procedure, and a letter from the licensee to the NRC dated May 4, 1982, indicate that the licensee's applies the procedures only to individuals who preform both safety-related work and who ,
compose the TS required minimum shift complement. In the letter on l May 4, 1982, the licensee also states that they interpret the TS to j apply only during operational conditions 1, 2, and 3. This 4 l
interpretation is based on a statement in the March 1981 LaSalle SER that overtime restrictions apply except for " extended periods of l shutdown for refueling, major maintenance, or major plant modifications."
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o x During the time period inspected for LaSalle (56 days). the amount of '
overtime worked in days of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> or longer by department, was noted as follows:
Operations - 196 instances where a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> day was worked Maintenance - 441 instances where a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> day was worked:
Radiological -L491 instances where a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> day was worked The total number of individuals working 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> days was not' determined.
As indicated in the data where individuals worked consecutive days with a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> shift per day, it appeared that operations personnel exceeded the 24 in 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> guideline on four occasions. Maintenance personnel exceeded the 24 in 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> guideline on 17 occasions. Radiation-Chemistry personnel exceeded the 24 in 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> guideline on 20 occasions. The inspectors determined that licensed operators met the policy but could not determine whether the other individuals were performing safety-related work as part of the shift to whom the GL 82-12 guidelines are applied or whether appropriate management approval was granted for this overtime.
1 Dresden: . Dresden is required by Technical Specification 6.2.A.14 to prepare, approve, and. adhere to detailed written procedures on working hours of the' Shift Engineer Station Control Room Engineer Shift Foreman, and Nuclear Station Operator job classifications such that the heavy use of overtime is not routinely required (a 15 with wording)nearly identical to the Dresden TS are in effect for Quad Cities and Zion . 4 Dresden has developed administrative procedure DAP 7-1, " Operations l Department Organization," to satisfy the TS. To strengthen admin-istrative controls, Dresden has also developed procedure DAP 7-21, (Revision 0, October 28, 1987), " Station Policy on Reactor Operator and Senior Reactor Operator Manning Levels and Overtime."
Dresden TS and procedures did not control the overtime of non-licensed operators, maintenance or rad ches personnel, however, in response to inspection report 237/8809(DRSS) a letter addressed to A. 8. Davis dated July 5,1988, the licensee comitted to applying guidelines to a " duty" radiation protection technician and a chemistry technician assigned to the safety-related duties. The licensee also provided the background of submittals made to satisfy NUREG-0737 Post-THI action item I.A1.3.1
" Limit Overtime". In attachment 1 of the response the licensee provided the following summary from a letter E. D. Swcrtz, Ceco Nuclear Licensing Administrator to D. G. Eisenhut. Director NRC Division of Licensing dated June 4, 1982:
- We are in substantial compliance with both the NUREG-0737 and Generic Letter 82-02 requirements. The subject overtime limitation for the Shift Engineer, Shift Foreman, Station Control Room Engineer and the Nuclear Station Operator is administrative 1y covered by procedure.
For the additional job classifications identified in the NUREG and Generic Letter, Dresden maintains a sufficient number of personnel such l that overtime, even for extended outages, is not routinely scheduled to extend beyond a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift. Per the November 10, 1981 letter from ,
T. A. Ippolito to L. De1 George, the NRC Ste.ff has found that our previous j 1
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correspondence adequately addresses the shift manning overtime limit requirements. This item is considered complete."
For the time period inspected for Dresden (56 days), the amount of
. overtime worked in days of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> or longer by department, was noted as follows: 7 Operations - 115 instances where a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> day was worked L
Maintenance - 124 instances where a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> day was worked l Radiological - 210 instances where a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> day was worked The total number of individuals working 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> days was not determined.
l As indicated in the data where individuals worked consecutive days with L a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> shift per day, it appeared that.the operations department exceeded th 24 in 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> guideline seven times, with three individuals working..three consecutive 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> days and one working four consecutive 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. days. Maintenance employees exceeded the 24 in 48 limit 15 times, with two individuals working four consecutive 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> days and lfive individuals working three consecutive 16' hour days. Radiation-Chemistry employees exceeded the 24 in 48 limit 40 times and the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> -
in 7 days limit on three occasions when individuals worked five consecu-tive 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. days. Individuals also worked four consecutive 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> days on 12 occasions and three consecutive 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> days on six occasions.-
7 The . inspectors determined that licensed operators met the policy but could not determine whether the other individuals were performing safety-related work as part of the TS minimum shift complement to whom the GL 82-12 guidelines are applied, or whether appropriate management approval was granted for this overtime.
Quad Cities: Quad Cities has a Technical Specification (6.1.A.14) on overtime with the same requirements as the Dresden TS. Quad Cities has
- procedure QAP 300-3, (Revision 10, July 22, 1988), " Shift Manning," to satisfy the TS.
As with Dresden, the NRC accepted ::ubmittals for Quad Cities including exceptions from procedurally controlling overtime hours for the additional job classifications identified in GL 82-12 1.e. health
. physicists and key maintenance personnel.
Zion: Zion has a Technical Specification (6.1.1.M) on overtime with the same requirements as the Dresden's TS. Zion procedure ZAP-0 (Revision 1, September 11, 1987), *Cenduct of Operations," was imple-mented to satisfy the TS and is also similar to Dresden's. As with Dresden, the NRC accepted submittals for Zion including exceptions from procedurally controlling overtime for health physicist and key maintenance personne1.
- 3. Allegation (99024)
-(Closed) Allegation (RIII-88-A-103), maintenance and operations employees are working a lot of long shifts. This allegation was substantiated in that overtime records indicated that in the two month period some individuals had worked several consecutive 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> days. The records 5 l l
a
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a L, did not show that single' individuals were consistently working long shifts but that the overtime usage was spread over a number of employees.
I NRC's position on use of overtime is described in the policy on " Nuclear
-Power Plant Staff Working Hours" which applies only to certain job classifications performing safety-related work. A great majority of t.
- worker overtime does not fall under this policy. In addition. Aafety-p related overtime work reviewed and approved by station management is permitted by the policy. No deviations from the policy were identified; this allegation is. considered closed.
,. 4. Conclusion l
The sites where overtime records were reviewed (Dresden, LaSalle and Braidwood) each have different commitments governing overtime which have been approved by the NRC. The applicable site procedures accurately reflect these consnitments.
The use of overtime as indicated by the work records reviewed did not indicate any gross failure to meet the overtime guidelines. The data also did not reveal that overtime usage by individuals covered by the .
policy was routine or heavy although a few instances of heavy overtime (three or more consecutive 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> days) were identified. The inspectors determined that none were licensed operators working without appropriate
- approval. In some instances where overtime use was heavy, it was not possible to determine if the overtime involved safety-related work requiring approval by management. Overall, there was significant overtime usage spread over a large population of employees. Although no deviations from the overtime policy were identified, the following concerns were raised:
- a. Some sites only apply the overtime guidelines to the TS minimum shift crew composition. This limitation does not appear justified .
~
as safety-ralated work is performed by personnel other than this crtw.
- b. Overtime policies are not being uniformly applied at all sites.
For example, at Dresden the overtime policy is applied to the Radiation Protection and Chemistry Technician positions. There is'no indication that the overtime policy is applied to this same position at the other five sites.
- c. Where the licensee committed to adequate staffing levels to meet the policy, it is not apparent from procedures or the time records provided that the licensee can effectively ensure that the overtime policy is being met.
- d. The LaSalle Station appears to apply the overtime policy only during plant modes 1, 2, and 3. It is not clear that the overtime policy is implemented during refueling or major outages.
These concerns were discussed by telephone with the licensee on August 2, 1989. During the discussion, the licensee informed Region III that Ceco was just completing an internal review on the same matter and would respond to the above issues in writing.
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