Similar Documents at Byron |
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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 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl 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 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 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 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 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 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 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 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 ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl 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) ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed 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 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 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.. 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 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 ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations 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) ML20207H7501999-07-12012 July 1999 Forwards Revised Pressure Temp Limits Rept, for Byron Station,Units 1 & 2.Revised Pressurized Thermal Shock Evaluations,Surveillance Capsule Rept & Credibility Repts, Also Encl ML20209G1391999-07-0909 July 1999 Forwards Results of SG Tube Insps Performed During Byron Station,Unit 1,Cycle 9 Refueling Outage within 12 Months Following Completion of Insps 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 ML20196K0161999-06-30030 June 1999 Discusses 990622 Meeting at Byron Nuclear Power Station in Byron,Il.Purpose of Visit Was to Meet with PRA Staff to Discuss Ceco Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff ML20196G2161999-06-25025 June 1999 Forwards for NRC Region III Emergency Preparedness Inspector,Two Copies of Comed Emergency Preparedness Exercise Manual for 1999 Byron Station Annual Exercise. Exercise Is Scheduled for 990825.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20209D4861999-06-17017 June 1999 Informs That R Heinen,License OP-30953-1 & a Snow,License SOP-30212-3,no Longer Require License at Byron Station 05000454/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed1999-06-0808 June 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed ML20207G0601999-06-0707 June 1999 Provides Updated Info Re Number of Failures Associated with Initial Operator License Exam Administered from 980914-0918. NRC Will Review Progress Wrt Corrective Actions During Future Insps ML20207G0421999-06-0404 June 1999 Forwards Insp Repts 50-454/99-04 & 50-455/99-04 on 990330-0510.Violations Identified & Being Treated as non-cited Violations ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207E5451999-05-28028 May 1999 Forwards Insp Repts 50-454/99-07 & 50-455/99-07 on 990517-20.No Violations Noted.Fire Protection Program Was Effective ML20211M1611999-05-28028 May 1999 Discusses 990527 Meeting with Comed Re Safety Culture & Overtime Control at Byron Nuclear Plant from Videoconference Location at NRC Headquarters.Requests That Aggressive Actions Be Taken to Ensure That Comed Meets Expectations ML20207D5261999-05-26026 May 1999 Forwards Response to NRC 990318 RAI Concerning Alleged Chilling Effect at Byron Station.Attachment Contains Responses to NRC 12 Questions ML20207B6361999-05-25025 May 1999 Forwards SE Accepting Revised SG Tube Rupture (SGTR) Analysis for Bryon & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20211M1781999-05-25025 May 1999 Summarizes Concerns with Chilling Effect & Overtime Abuses at Commonwealth Edison,Byron Station.Request That Ltr Be Made Part of Permanent Record of 990527 Meeting ML20195C7911999-05-25025 May 1999 Forwards Revised COLR for Byron Unit 2,IAW 10CFR50.59.Rev Accounts for Planned Increase of Reactor Coolant Full Power Average Operating Temp from 581 F to 583 F 05000454/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed1999-05-21021 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed ML20206U3471999-05-20020 May 1999 Forwards Insp Rept 50-454/99-05 on 990401-22.No Violations Noted.Insp Reviewed Activities Associated with ISI Efforts Including Selective Exam of SG Maint & Exam Records, Calculations,Observation of Exam Performance & Interviews ML20207A2151999-05-19019 May 1999 Forwards Insp Repts 50-454/99-06 & 50-455/99-06 on 990419-23.No Violations Noted.Insp Consisted of Review of Liquid & Gaseous Effluent Program,Radiological Environmental Monitoring Program,Auditing Program & Outage Activities 1999-09-08
[Table view] Category:NRC TO EDUCATIONAL INSTITUTION
MONTHYEARML20212P1851987-03-11011 March 1987 Responds to 870309 10CFR2.206 Petition for Commission Review of Director'S Decision DD-87-2.Time Period for Commission Review Expired & Decision Became Final Agency Action on 870310.Served on 870312 ML20055C0451982-08-0606 August 1982 Forwards Region 3 to Licensee & Notice of Violation & Imposition of Civil Penalty for Zion Facility.Proposed Fine Not Indicative of Future Level of Performance of Byron Plant Mgt 1987-03-11
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M2871999-10-21021 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 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 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 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 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 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 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 ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations 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) ML20196K0161999-06-30030 June 1999 Discusses 990622 Meeting at Byron Nuclear Power Station in Byron,Il.Purpose of Visit Was to Meet with PRA Staff to Discuss Ceco Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20207G0601999-06-0707 June 1999 Provides Updated Info Re Number of Failures Associated with Initial Operator License Exam Administered from 980914-0918. NRC Will Review Progress Wrt Corrective Actions During Future Insps ML20207G0421999-06-0404 June 1999 Forwards Insp Repts 50-454/99-04 & 50-455/99-04 on 990330-0510.Violations Identified & Being Treated as non-cited Violations ML20207E5451999-05-28028 May 1999 Forwards Insp Repts 50-454/99-07 & 50-455/99-07 on 990517-20.No Violations Noted.Fire Protection Program Was Effective ML20207B6361999-05-25025 May 1999 Forwards SE Accepting Revised SG Tube Rupture (SGTR) Analysis for Bryon & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20206U3471999-05-20020 May 1999 Forwards Insp Rept 50-454/99-05 on 990401-22.No Violations Noted.Insp Reviewed Activities Associated with ISI Efforts Including Selective Exam of SG Maint & Exam Records, Calculations,Observation of Exam Performance & Interviews ML20207A2151999-05-19019 May 1999 Forwards Insp Repts 50-454/99-06 & 50-455/99-06 on 990419-23.No Violations Noted.Insp Consisted of Review of Liquid & Gaseous Effluent Program,Radiological Environmental Monitoring Program,Auditing Program & Outage Activities ML20207B8751999-05-18018 May 1999 Responds to Ltr Dtd 990225,expressing Concerns That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazards at Some Commercial Nuclear Power Plants in Us ML20206N4791999-05-13013 May 1999 Forwards RAI Re 980529 Amend Request for Byron & Braidwood to Credit Automatic PORV Operation for Mitigation of Inadvertent SI at Power Accident.Response Requested 60 Days After Receipt Date ML20206J1981999-05-0505 May 1999 Forwards Exam Answer Key for Forms a & B,Grading Results for Facility & Copies of Individual Answer Sheets for Each Individual Taking Gfes of Written Operator Licensing Exam Administered by NRC on 990407.Without Encls ML20206E7021999-05-0303 May 1999 Advises That Info Contained in Document Entitled, Licensing Rept for Sf Rack Installation at Byron & Braidwood Stations, HI-982083,will Be Withheld from Public Disclosure Per 10CFR2.790 ML20206D0361999-04-28028 April 1999 Confirms Plans to Have Meeting on 990527 in Lisle,Illinois to Discuss Results of Ceco Evaluation on Potential Chilling Effect Concern within Working Environ & Use of Overtime within Operations Dept Organization at Byron Station ML20205Q2621999-04-14014 April 1999 Forwards Insp Repts 50-454/99-03 & 50-455/99-03 on 990217-0329.Five Violations Identified & Treated as Ncvs. Expresses Continued Concern with Configuration Control & Human Performance Errors at Byron Station ML20206U3261999-03-29029 March 1999 Forwards RAI Re 981208 Response & Suppls to NRC Re Use of Overtime in Byron Station Operations Dept.Response Requested within 30 Days of Date of Ltr ML20196K8821999-03-26026 March 1999 Advises of Completion of Plant Performance Review on 990201 to Develop Integrated Understanding of Safety Performance. Overall Performance Acceptable.Plant Issues Matrix & Insp Plan Encl ML20205B4901999-03-26026 March 1999 Forwards SER Authorizing Util 981022 Relief Requests 12R-24, Rev 0,which Requests Deferral of Rv shell-to-flange Vessel Weld Exam to End of Second 10-year Insp Interval,Pursuant to 10CFR50.55a(a)(3)(ii) & 12R-34,rev 0 ML20204G3641999-03-19019 March 1999 Forwards Safety Evaluation & Technical Ltr Rept Re Second 10-yr Interval ISI Request for Relief 12R-11,rev 2.Licensee Proposed Alternative to code-required Pressure Test Authorized for Current Interval ML20204E2631999-03-18018 March 1999 Discusses Review of Ceco Evaluation of Chilling Effect on Byron Station Personnel.Identified Number of Questions Re Ceco Findings & C/As.Requests Further Evaluation of Chilling Effect at Byron Be Conducted & Response to Encl Questions ML20204D1971999-03-16016 March 1999 Discusses Review of Revision 4Q to Portions of Licensee Emergency Plan Site Annex ML20204B6721999-03-12012 March 1999 Forwards Copy of Preliminary Accident Sequence Precursor Analysis of Operational Condition Discovered at Plant on 980912 ML20207K1861999-03-11011 March 1999 Discusses Review of Rev 4P to Portions of Byron Power Station EP Site Annex.Based on Determinations That Changes Do Not Decrease Effectiveness of EP & Plan Continues to Meet Standards of 10CFR50.47(b),NRC Approval Not Required ML20207J5201999-03-10010 March 1999 Forwards Insp Repts 50-454/99-02 & 50-455/99-02 on 990105-0216.No Violations Noted.Expresses Concern Re Trend of Configuration Control & Human Performance Errors at Byron Station ML20203G7981999-02-11011 February 1999 Forwards Insp Repts 50-454/99-01 & 50-455/99-01 on 990119-22.No Violations Noted.Insp Involved Exam of Maint & Engineering Related Activities for Electrical Circuit Breakers ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203C9861999-02-0808 February 1999 Ack Receipt of ,Which Transmitted Changes Identified as Rev 52 to Security Plan.No NRC Approval Required ML20202H9401999-02-0303 February 1999 Informs That Update of Set Number 58 of UFSAR Has Been Completed.Confirmation Sheet Providing Update Encl ML20199H8561999-01-19019 January 1999 Discusses Insp Repts 50-454/98-25 & 50-455/98-25 on 981124-990104 & Forwards Nov.Violation Identified Involving Unacceptable Preconditioning of Stroke Time Testing of AFW Pump Discharge Valves ML20199E8861999-01-15015 January 1999 Discusses Two Unresolved Security Items Identified in Sections S3.b1 & S3.b2 of Insp Repts 50-454/98-03 & 50-455/98-03,dtd 980211.One Item Re Adequacy of Alarm Sys Testing When Two Alarm Zones Were Returned to Svc ML20198N8261998-12-30030 December 1998 Forwards Insp Repts 50-454/98-24 & 50-455/98-24 on 981130- 1204.No Violations Noted.Purpose of Insp Was to Determine If Licensed Operator Requalification Training Activities Conducted IAW with NRC Requirements ML20198J0211998-12-18018 December 1998 Forwards Insp Repts 50-454/98-20 & 50-455/98-20 on 981006- 1123.No Violations Noted ML20198F4451998-12-17017 December 1998 Forwards Insp Repts 50-454/98-23 & 50-455/98-23 on 981116-14.No Violations Noted.Purpose of Insp Was to Verify Accuracy of Licensee Response to Region III Questions Re Grid Stability ML20206N4431998-12-10010 December 1998 Forwards Security Insp Repts 50-454/98-22 & 50-455/98-22 on 981116-20.No Violations noted.Challenge-testing of Some Detection Equipment Showed Some Vulnerabilities That Util Indicated Would Be Corrected 1999-09-08
[Table view] |
Text
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Professor Bruce von Zellen Northern Illinois University Department of Biological Sciences DeKalb, IL 66105 In the Matter of COMMONWEALTH EDISON COMPANY (Byron Station, Units 1 and 2)
Docket Nos. 50-454, 50-455
Dear Professor von Zellen:
I am in receipt of your letter of July 22,1982(copyattached) regarding a fine proposed on July 9,1982 by the NRC for imposition upon the Applicant for an overexposure incident at the Zion plant. A copy of the NRC letter to the Applicant and the notice of violation and proposed imposition of civil penalties is enclosed.
As stated in the attached affidavit of William L. Forney, despite the large amount, this fine, if imposed, would be the first fine imposed at Zion in four years and the first imposed on the Applicant this year.
The proposed fine is not indicative of the future level of performance of Byron plant management and does not change his overall conclusion on Contention 1. See affidavit of William Forney accompanying the July 14 Staff response to Applicant's motion for summary disposition of DAARE/ SAFE Contention 1.
Sincerely, A< L E{. fr-u uf
. Mit * . Young Counsel for NRC Staff Enclosure as stated l cc: (w/ enclosure) service list DESIGNATED ORIGINAI.
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- l Docket No. 50-293 License No. DPR-39 l EA 82-78 l
Coemonwealth Edison Dorpany ATIN: Mr. James .7. D'Connor President i
Test Office Box 7&T -
l Chicago, IL 60690 -
Centlement i
nis refera to the specl&) Insped}on conducted by liessr&. b. f,. bilier and
' L. R. Greger of our Region III staff on Harch 30-31 April 7-6, and 29,1982 .
of activities at the Zion h'ucle&r Poser station, hit 1. In Zion, Illinois, authorf red by KRC Operating License h*o. DPR-39. H e results of this special inspection were discussed on April 17. 1982 during an enforcement conferenc4 at the NRC Region III Office between Mr. t. Reed and others of your staff and Mr. J. Keppler and others of the RRC staff. The special inspectlen was con-ducted to review the circunstances hurrounding the overexposure received by a worker during an entry beneath the h it i reactor vessel (reactor cavity) en March 25, 1982.
1 The results of thi Inspecl$on IndicAtk &Erfout weaknesses in your radiation
'- protection prograr. concerning systecatje evaluation and planning of radiation work. Specific weaknesses exhibited in this incident include: (1) lack of I
coordination between plant health physicists And rad /cher foremen in planning the entries, (2) Anadequate radiation surveys associated with the entries, (3) use of inexperienced rad /ches technicians to monitor the entries, (4) lack of understanding by radiation protection personnel of the reactor cavity radio-logical hazards including the radiation tources (3) Anadequate training in reactor cavity radiological hazards even though & tiellar overexposure had occurred in 1976, (6) failure of shift operations personnel in leadership positions to exhibit good radiation protection practices, And (7) unevailabil-ity of survey instruments calibrated to greater than $0 R/hr.
k*e consider the breakdown In kanskemeni. tontro}s khich Aihed this overexposure to occur to represent herloui programatic L eeknesset in your radiation protec-tion program, k'e are particularly concerned that this overexposure occurred 1 I CERTITIED MAIL ffETLTM T5MDTMf Ff6t@Jtsf@il
Comonwealth Edison borpany A a' July I,1982 even though you lepleeented Actions to preclude 6uch an occurrence es & result of a similar overexposure et Zion, Unit 1 in 1976 and in response to It Circular 76-03, which warned of the potential radiation hazards Ass.ociated*with PWR re'ector cavities. Our concerns kere discussed kith your representatives durin&
the enforcement conference At the Region Ill of fice. Although the correctiva actions proposed during the enforcement conference and th your keportabla Occurrence Repprt dated Ap:11 23, 1982 generally represent positive steps to resolve our concerns, additional Actions Are required.
After consultation with the Director of the Offlet of inspection and Enforcement.
I have been authorized to issue the enclosed h'otice of Violation and Proposed leposition of Civil Penalties in the ar.ount of One Hundred Thousand Dollars. la assessing these civil penalties we gave consideration not only to the circum-stances described above which led to the violations At issue but also to the prior notice (IE Circular 76-03) and civil penalties for sia;ilar events at this facility and elsewhere. These considerations resulted in proposed civil penal-ties of $100,000 because we believe & herious breakdown in kanagement controla and your radiation protection prograns occurred which resulted in in unnecessary exposure.
- In your response to this $etter, please follow thi $nstructions $n the Itotica.
' Your response should specifically address the weaknesses noted above, corrective actions you have taken or plan to take to leprove the sansgesent effectiveness of your radiation protection program, And your plans to provide & high level of l assurance that unnecessary exposuret resulting free 6ntry into the reactor cavity will not occur stein at the Zion f acility. Tou should consider engineer-Ang controls, such es & camere eonitoring syster. er a leak detection systes, to eliminate the need to enter the reactor cavity when incere thlebles or detectors are withdrawn. You thould 41so consider autozatit tystems And procedural controls for preventing reactor cavity entries when high radiation levels exist and procedural controls to rinleine the time the incere thimbles or detectors are in unshielded positont. Your response should include an analysis and rationale for your conclusions regarding these considerations.
Your written reply to this letter and the results of future inspections will be considered in determining whether further enforcement action is appropriath.
In accordance with section i.790 of the NRC*t " Rules of bractich," Part 2 6 Title 10, code of Federal Regulations, a copy of thik letter and the enclosura vill be placed la the NRC Public bocument Room.
S e
W h
l
.j u y'l h, 1985 Comonwealth Edison borpiny ')&
t i ne response directed by thjt jelikt and th6 Mciosed Notjck krh not subject d to the clearance procedures of the Offici of kanagerent ind ludset* is seguire by the Paperwork Reduction Act bi 1980. F1,96-311.
blnckrk))4 janei 6. keppleir itegional Administritor i
i Inclosure:
NoticeofV3olationkndfropossd Imposition of Civil Penaltlet
IllinoisDepartzentofNuciairkabi) '
~
AT1%: Dr. Philip t. Custafsos - .
Director ~
1035 Outer Park briv&
Springfield, IL 62708 .
Tyrone C. Tahner Attorney Genersi of 1111mbl&
500 5. Second St.
Springfield. IL 627M l
I Michael V. Hasten, Chiirsin l Illinois Connerce Co::cisalon
! 527 E. Capitol Ave. .
Springfield. IL 62708 .
e 4
ND71Cl 6T V101AT10M Am MPOPOSEb l*: POSITION OF CIVIL hENALTitt Co.anonwenith Edison Comp &ny M ket No. $0-19$
Zion Nuc1sar Power station Licensa No. DPA-39 ,
1A 42-74 Unit 1 I
As a result of an inspection conduct 4d harch 30-31 and April 1-I. and N .
l 1982 at the Zion Nuclear Power Station. Unit 1. In Zion. Illinois. It j
appears that significant problems in the inplerentation of the licensee's t
health physics program resulted in en overexposure incident. The ifconsee
! failed to make adequate evaluationt of radiation horards before entries into an area beneath the Unit i reactor vessel, 4 high radiation area, and infled to ensure that en individu&l kould not he exposed to a radiation .
dose in excess of regulatory limith.
l In accordance with the h*RC knforcement Polic (10 brR fart I Appendia 5) *
! 47 TR 9987 (March 9, 1982). And pursuant to action 234 of the Atoele l
Energy Act of 1954 es 6 tended ("Act"), 42 t!.$.C. 2282, PL 96-29$. &nd 3
10 CFR 2.205, the particular violations and the Assotiat6d tivil penaltiat
- are set forth belout 1
A. 10 CrR 20.201(b) requires that each 15censee makt er cause to he made such evaluations of radiation hazards es (1) may he necessary for the
- licensee to comply with the regulaticns in 10 CTR Part 20, and (2) ar6 reasonable under the circumstances to avaluate the extant of radiation hazards that may be present.
Contrary to the above, ih ileensee failed to make tuch radiation aval-untions at were necessary And reasonable under the circumstances to ensure compliance with 10 CTR 20.101 for entries of individuals into l
an area beneath the Unit i reactor vessh) on.harch 24 and 25,1982.
1his is a Severity level ill idoihtlon (8vpplemeni kV).
(Civil Penalty - $70,000).
- 3. 10 CTR 20.101(a) limits the whole body radiation dose of Any individ-val in a restricted area to one and one quarter rees per calendar quarter, except es provided by 10 CTR 20.303(b). Paragraph (b) permits
. a whole body dose of three rems per calendar quarter provided certain
. specified conditiont Are met.
a, t
4
, Notice of Violation I Contrary to the &bov6, durin thefirsttelenderquart6rof1941.An individual received 4 whole body dose of approximately five rest.
Most of this dose kes received khile asking an entry into the tras beneath the Unit i reactor vessel on Hare.h 25 6 1982.
This is 4 leverity 1,evel ill tlotation (suppiesent IV).
(Civil Pensity - $30,000).
Pursuant to the provisions of N CFR I.201. Conconwealth tdison Coeipany is hereby required to submit to the birector. Office of Inspection and Enforcement. USNRC. 4'ashington. DC 20$$$. And 4 copy to the Regional Administrator. USNRC Region III. kithin 30 days of the date of thle Notice a written statement or explanation including for each alleged violation: (1) admission or denial of the alleged violation; (2) the reasons for the violation if 6deftted; (3) the corrective steps which have been taken and the results achieved; (L) the corrective steps which will be taken to avoid further violations: And ($) the date when full compliance will be achieved. Donsideration ony be given to extending the response time for good cause shown. Under the authority of Section i 182 of the Act, 42 U.S.C. 2232, this response shall be submitted under oath or affirmation.
l k'ithin the same time As provided for the responte required above under 10 CFR 2.201, Coernonwealth Edison Company may pay the civil penaltiat in the cumulative amount of one Hundred Thousand Dollars or may protest imposition of the civil penalties in whole or in part by a written answer.
Should comonwealth Edison company fall to answer within the time specified.
the Director, Office of Inspection &nd Enforcement will issue an order imposing the civil penalties in the amount proposed above. Should Coanonwealth Edison Company elect to file an answer in accordance with 10 CFR 2.203 pro-testing the civil penaltiets kuch answer may (1) deny the violations listed in this Notice in whole or in parti (2) demonstrate extenuating circumstances; (3) show error in this Notice; or (I.) show other reasons Why the penalties should not be imposed.
In addition to protesting the tivli penaltiet in Whole or in part. 6uch answer may request remission or mitigation of the penalties. In requesting mitigation of the proposed penalties, the fise factors contained in Section I IV (B) of to CrR part 2. Appendix C should be addressed. Any written answer in accordance with 10 CTR 2.205 should be set forth separately from the statement or explanation in reply potate by specific reference (e.g. pursuant to 10and titing page CTR 2.201, but paragraph may Jncor-numbers) to L.
1 g
s
5 Notice of Violation avoid repetition. Dommonwe<h tdison'toepany's ettention for 16imposing directed to the other provisions of 10 CFR 2.203, regarding the procedurb a civil penalty.
Uponfailuretopayanyelvlipensitlekdu6.khldshavebeensubsequently determined in accordance with the App)f cable provisions of li30 CTR 2.20$. -
this matter any be referred to the Attorney General, and the pena t ese l unless compromised, reeltted, or altigated. tay be collected by civi action pursuant to Section 234c of the Act. 42 U.R.C. 2282.
Itk THE h'UC12AR kEGUll1VRY COE15$10 james C. keppler Regional Administrator Dated at Glen Ellyn. 1111nols this day of July 1981
. A M. _
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