Similar Documents at Byron |
---|
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: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
_ _ _ _ _ _ _ _ . _ - . _ _ . . _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
August 1. I TH a.e
-n-CA 97 200 ] ](T D Mr. K. Graesser Sito VsCO Pr05idOnl Byron Station Commonwealth Edison Company 4450 N. German Church Road Byron, IL 61010
SUBJECT:
NRC PREDECISIONAL ENFORCEMENT CONFERENCE REPORT
Dear Mr. Graesser:
This refers to a Predecisional Enforcement Conference conducted by Mr. A. B:ll Beach, Regional June Administrator, end other members of the Region 111 and Headquarters staff on 20,1997.
The sub}ect of this conference was the apparent violations at Byron Station identitled in NRC Inspection Report Nos.
50 454/97005(DRP): 50 455/97005(DRP) concerning the blockage of the Unit 2 containment floor drains. We have enclosed a
' partiallist of attendees (Enclosure 1) and a copy of the handout you provided during the conference (Enclosuro 2).
You will be notiflod by separate correspondence of our decision regarding the enforcement action based on the information presented and discussed at the Predocisional Enforcement Conference. No responso is required until you are notified of the proposed enforcoment action, in accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter and the enclosed report will be placed in the NRC Public Document Room.
We Conference.
will gladly discuss any questions you have concerning this Predocisional Enforcement Sincerely,
\
/s/ M. Dapas for Geof froy E. Grant, Director Division of Reactor Projects Docket Nos. 50 454; 50 455 Licenses Nos. NPF-37: NPF 66
Enclosure:
NRC Predecisional Enforcement Conference Report SAqAltached Olstribution and Concurrene_q 1.DOCUMENT % . n . w. NAME: 4 G:\BYRO.lR\BYR97005.ENF wa v . m. n w v wi c - con .*i i .a-e- au..a t . con e .a.a .u.aa..
OFFICE Rill Rlli Rill Ritt Rill NAME- TTongue:nh RLanksbury HClayton BBorson DATE 081 /97 GGrant 081 /97- 08/- /97 08/ /97 08/-/97 OMICI AL fiEUDhD~CDFY OR
e N e August 1, 1997 I l
EA 97 200 !
1 fAr. K. Grausser 1
Sito Vice President i ilyton Station - !
Cominonwealth Edison' Company 4450 N. Gerrnan Church Rnad j Byron, IL - 61010 i t
SUBJECT:
NRC PREDECISIONAL ENFORCEMENT CONFERENCE REPORT
Dear Mr. Graesser:
This refers to a Predecisional Enforcement Conference conducted by Mr. A. Bill Bea Regional June Administrator, and other members of the Region 111 and Headquarters staff o 20,1997.
, The sub}ect of this conference was the apparent violations at Byron
- . Station identified in NRC inspection Report Nos. 50 454/97005(DRP); 50 455/97ii concerning the blockage of the Unit 2 containment floor drains. We have enclosed a -
~ teport surnmarizing the discussion. ,
4 .
You will be notified by separate correspondence of our decision regarding the enforcI action based on the information presented and discussed at the Predecisional Enfor Conference.
action. No response is required until you are notified of the proposed enforcemen
~
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter ?
and the enclosed report will be placed in the NRC Public Document Room. ;
We will gladly discuss any questions you have concerning this Predecisional Enfcrcem Conference.
1 Sincerely, i
/s/ M. Dapas for >
Geoffrey E. Grant. Director Division of Reactor Projects Docket Nos. 50 41,4; 50-455 .;
Licenses Nos. NPF 37; NPF-66 :
Enclosure:
NRC Predecisional Enfcrcement Conference Report See Attached Distribution '
- i.m.i DOCUMENT NAME: G:\BYR
= . m.
. .,m.- me Om lRtBYR97005.ENF m.e. e c m .e-,
~ t . cm .u.e==.s __
OFFICE Rill Y. Rill : y, Ritt .
NAME TTongue:rhet Alanksburg HCleyto" AC.,
.Q IR- -/ Rill - ( .,
I DATE 08/or/97.
BBerg GGrantg@
'08/d//97 ' 08/*l/97 7/97N {
OFFICIAL RECORD COPY . 08// /97
~
~
,,, _ _ _ ___,c__.,_ . .. .. _ .._._u-.
._.-. , _ _ _ ~ .
, s K. Graessor 2-cc w/o encti T. J. Maiman, Senior Vice President Nuclear Operations Division D. A. Sagor, Vice President, Generation Support H. W. Keiser, Chief Nuclear Operating Officer K. Kofton, Station Manager D. Brindle, Regulatory Assurance Supervisor- -
- l. Johnson, Acting Nuclear Regulatory Services Manager cc w/ encl: Richard Hubbard Nathan Schloss, Economist Office of the Attorney General State Liaison Officer, Wisconsin -
State Liaison Officer Chairman, Illinois Commerce Commission Document Control Desk l.icensing i
DJstribution:
~ ,
Docket File w/enci OC/LFDCB w/enci SRI Byron, Braldwood, Zion w/ encl QRP w/enct Project Manager, NRR w/enct fUBLIC IE 01 w/enct
, A. B. Beach, w/enct CAA1 w/enci (E mail)
. Rlli Enf. Coordinator, w/enct RAC1 (E Mail) w/ encl Deputy RA, w/ encl ;
Rlli PRR w/enct TSS w/enct DRS (2) w/enci -
J. Lieberman, OE DOCDESK (E-mail)
J. Goldberg, OGC R. Zimmerman, NRR ;
l 1
+
i-ll [
j:
l ,
___a-er v-e m 4"~ ' * ' ** ~
e i j P
I Enclosure 1 i
1.
Dttial List of PQfiQns. Pros 20t at Conference Commonwo3htLEdison Comnany (Comed)
K. Graesser, Site Vice President I
K. Kofron, Plant General Manager "
T. Gierith, Operations Manager D. Wozniak, Engineering Manager D. Brindle, Regulatory Assurance Supervisor U..SmNucleaLBagulatorv commlanlon A. B. Beach, Regional Administrator, Rlll G. Grant, Director, Division of Reactor Projects R. Capra, Director, Project Directorate 1112, NRR -
J. Jacobson, Acting Deputy Director, Division of Reactor Safety
- B. Berson, Regional Counsel R. Lanksbury, Chief, Projects Branch 3 T. Tongue, Projects Engineer '
N. Hilton, Resident inspector K. Selburg, Radiation Specialist During the meeting the apparent violations identified during the inspection were discussed, along with the corrective actions taken or planned by you. The apparent violations involved: (1) failure to meet the Technical Specification action statement when the Unit 2 containment floor drain system was inoparable; and (2) failure to conduct a 10 CFR 50.5g safety analysis for a modification to the Unit * ~ '
2 containment floor drain grates that were not as described in the UFSAR.
9 V
=
- p. w,73 9 ,Awg-p--.9y g -9 gass ee --g-p e yw y 3gg 7,y y grin 7p;41y,.q fir e trw W- m,- q,ii,-yem---t w y ,-- wo ww wa-w-mm E-v' ee '-we-_wwu----
car 2
~
j Byron Nuclear Power Station i
- i I
i CONTAINNIK5T FLOOR
~
DRATN SYSTEMISSUES i i
I i
l PRE-DECISIONAL ENFORCEMENT CONFERENCE .
JUNE 20,1997 REGION III
1 AGEXDA -
f Opening Remarks K. Graesser 4 -
RF System Description, D. Wozniak 50.59 Issue and System Operability Issue Operator Identification Issue T. Gierich LERIssue D. Brindle Conclusions K. Graesser .
1 I 2
Opening Remarks Apparent violations
-No safety evaluation Agree
-RF system inoperable Disagree
-Opportunity to identify inoperability Disagree
-Inaccurate LER Disagree i
m v.
_ . _ _ _ . _ _ __ __ _ _ . - -_ m + - - = ' - ' ' - - - ' - "- *
*4 -- ^- " " ' ^ ^ "
4 4
CONTAINMENT BUILDING FLOOR DRAIN SYSTEM BLOCK DIAGRAM I
i UWTAMENT OUTER TRENCH Elev. 377'
. I
) j (
/
/
RcreoRan r
g f l > \
\
7 f
~
^
/
) ,f1 i I
(
\
x v ' \ I '
r BARRER
"" "a"Ev=M N -
u._.s
_m_ -
m__
.... zz.
"oe Yw i
g so-
\ WERBOK OLSTORAGE VAULT
Lack Of 50.59 For Missing Grating '
i -
Self-identifiec FSAR description does not match as-built plant No 50.59 safety evaluation performed Floor drain bar grates not installed per drawings Several different type drain grates installed Condition existed since original construction Plant configuration must be consistent with FSAR 5
1 .
L
- Lack Of 50.59 For Missing Grating - cont.
t Corrective Actions
- Lessons learned from SX event -
- Operability assessment was performed
- RF system was determined operable ,
- Long term actions to be completed during each unit's next refueling outage i
4 6
Lack Of 50.59 For Missing Grating - cont. -
4 Safety Significance -
i
- Health and safety of public not impacted
- Safe shutdown systems not affected
- Safe reactor conditions maintained t
7 !
Degraded RF System -
RCFC Surveillance
- Investigated surveillance dates
- - Investigated chart recorder traces
- - Data shows atypical characteristic curves 4
F
)
8 S
~
RF ALARM & CHART RECORDER ACTIONS FOR PERIOD OF 10/27/96 -04/18/97 Page 1 of 2 .
DATE EVENT SER CHART POINT SUMP sunu nec. msr. s.Even.
REMARKS RESPONSE CHANGE 10/27/96 Monthly Surveillance NO NO NO l 0.0 gpm l 11/10/96 UNUSUAL YES YES YES l 1.7 gpm l Performed 2BOS RF-1/ Containment entry /P!F 455-201-96-0681 11/25/96 Monthly Surveillance YES *NO YES l 0.6 gpm l *Recorderwas not inking 11/27/96 RCFC Starts and Stops NO *NO YES l 0.2 gpm l
- Recorder was not iniung for Chi!!er work l l 12/02/96 RCFC Start for Chi!!er NO YES YES l 0.3 gpm l Chart recorder indicated max input of 0.6 gpm work l l 12/09/96 RCFC Start NO NO NO l 0.02 gpm l Short duration run, no level increase detected 12/27/96 Monthly Survaillance YES YES YES l 0.3 gpm l Chart recorder showmg approx. 0.65 gpm 01/22/97 Containment Release m YES- YES~ YESn ~ l: - l Chart Recorderincreased approx. 0.5 opm to 1.0 gom 01/24/97 Month!y Surveillance YES YES YES l 0.3 gpm l Chart Recorderincreased approx. O.3 gpm to 1.0 gpm l l l (Alarm came in from 1030-1512 & 1758-1836) 01/28/97 Containment Release ? YES YES YES9 311 m l Chart Recorder increased approx 0.45 opm to 0.75 gom
~01/3Of97 Containment Release : .YESt YES ?" YESjg ~^
Chart Recorder increased hoprom 0.5 gpm to 0.8 gpm i-
, , QT ~ L j* ^j ** .A X PF 455-201-97-0046 generated due to continued reading of 1
,a. %x j ne - ~ "
' _~ 0.6 gpm on recorder .
01/31/97 Containment R*8a=== ' YES; YESw + YES<:15 - "I Chart Recorderincreased approx. 0.3 gpm to 0.9 gyc '
024Mt97 Containment Release YESU YES ~M YES?l:
'l Chart recorder increased =aarox. 0.45 mm to 0.75 com 02/04/97 Alarm @ 0709 YES YES YES Chart recorder increased appicx. 0.15 gpm to 0.9 gpm /
Perforrned 2BOS RF-1 02/05/97 Stop/ Start 2C RCFC YES YES YES l 0.1 gpm l Chart recorder increased approx. 0.15 gom to 0.9 gpm -
02/05/97 Alarm @ 1422 YES YES YES l '-e l Chart recorder increased approx. 0.15 gpm to 0.9 gpm 02/05/97 Restart of Cntmt Chiller YES YES YES l r+'-' l Chart recorder increased approx. O.15 gpm to 0.9 gpm 02/06/96 Alam @ 1439 YES YES YES Chart recorder increased approx. 0.15 gpm to 0.9 gpm .
Performed 2BOS RF-1 02/07/97 CwL,e..i Release F y YES< = YES'r T - Chart Recorder increased approm 0.4 gpm to 1.0 gpm -
02/08/97 Alarm @ 1300 , YES YES Chart Recorder increased approx. 0.15 gpm to 0.9 gom t I
i s
M' RF ALARM & CHART RECORDER ACTIONS FOR PERIOD OF 10/27/96 - 04/18/97 Pagelof 2 -
DATE EVENT SER CHART POWT SUMP AuRM REC. MST. 1.EVEL REMARKS RESPONSE CHANGE 02,09/97 YES YES '
Alarm @ 0507 YES ~ Chan Reccrder maintamed appicx. 0.7 gpm / 1 2BOS RF-1 Performed 1 02/09/97 Alarm @ 1351
~
YES YES YES Chart recorder increased appicx. 0.1 gem to 0.7 gpm 02/10/97 CvinJod Reisase YESJ YES~ YES :lr =- - l Chart recorder mcreased marwox. O 45 pn to 0.9 gom L i
02/12/97 Containment Reloose YESS YES: ^ YES F l + a =il Chart recorderincrsesed maaror 0.4 @n to 0.9 gom 02/13/97 Alarm @ 1113 YES YES YES Chart Recvider slight increase / reading 0.65 gpm (0.65 - 0.75 i gpni has been baserine since 01/30/97) Perferined 2BOS RF-1 02/14/97 Contamment Release. YES 1 YESa ( YES~ ' ~ ^ i Chart recorder mcreased approx 0.45 gom to 0.9 ppm 02/16/97 YES YES YES Chart Recorder shows a x. 0.9 .
/ Performed 2BOS RF-1 02/17/97 Alarm @ 0334 YES YES YES Chart Recorder shows appror 1.0 gpm / Performed 2 SOS RF-1 02/17/97 Containment Release " YES- YES: YES: " Chart Recorder increased approx. 0.4 w i 101.2 gr u 02/17/97 Alarm @ 1802 YES YES YES Chart Recorder reading is approx.1.05 gpm 02/18/97 Start 2A RCFC Fan / YES YES YES l 024 gpm [ Performed in attempt to clear weir of debns /
Stop 2B RCFC Fan l i
l Flow increased from aoprox. 0.9 gom to 1.2 gom 02/20/97 Containment Release YES YES c YES : : l: - > l Chart Recorder meressed approm 0.3 gpm to 1.1 com 02/21/97. Containment Release YES5 YES- YES : 11 F;1 Chart Recorder increased approx. 025 gpm to 1.0 ppm 02/21/97 Monthly Surveillance YES YES YES l 0.13 gpm l Chart Recorder increased approx. 0.2 gpm to 0 9 gpm / (Atarm l l came in from 1538-1622 & 1916-2210) / Performed 2 SOS RF-1 02/24/97 Alarm @ > 01 YES YES YES Chart Recorder increased appicx. 0.4 gpci to1.0 gpci /
Performed 2BOS RF-1 02/25/97 Cci&Vi=4 Release YES' YES1 YESCl+ ' l Chart Recorder irx:ressed approx. 0.4 apm to1.2 gpm 02/25/97 Alas @ 0317 YES YES YES Chart Reccider increased approx. 02 gpm to1.0 gpm /
PerfenTE-d 2BOS RF-1 i
03/08/97 Sic' 2A'RCFC Fan / NO YES YES l 02 gpni l Chart Recorder increased approx. 0.2 gpm Start 2B ROFC Fan l l 03/21/97 Monthly Surveillance YES YES YES l 12 gpm l Chart Recorder increased approx. 2.0 gpm / i l ] (Alarm came in from 1300-1334) l 04/18/97 MiEly Surveillance NO YES E l 0.S gpm l Chart Recorder increased to approx. 0.75 com 1
}
l
e Degraded RF System - cont.
~
For each event received response from either the Significant Events Recorder, chart recorder, or alarm '
For single RCFC starts / stops, we expect to see no l
change Shift noted chart recorder not functioning l
Actions taken to verify aroper weir operation l
i j
i
Degraded RF System - cont. -
Root Cause
- Debris in floor drain system
- Flow control device restricted 4
- Drain bar grates missing or deteriorated
- Drain bar grates not installed according to design requirements
- Containment floor drain trough not according to design i
drawings d
j 11
Degraded RF System - cont. ~
Safety Significance
- Health and safety of public not impacted
- Safe shutdown systems not affected
- Safe reactor conditions maintained i 12
Degraded RF System - cont.
~
Corrective Actions
- RF System Activities (3/15 - 21/97 & 5/31 - 6/3/97)
Inspected and cleaned floor trench drains inside/outside missile barrier Visually inspected and cleaned weir box, oil separator, sump Flushed flow control device and associated piping Calibrated instrumentation 13
Degraded RF System - cont.
Corrective Actions - cont. -
- RF System Activities (11/07/97 & 4/5/98)
Hydrolaze floor drain system Install new bar grates Flush flow control device and associated piping Remove oil from oil vault .
Inspect and clean oil separator, weir box ;
Dewater sump to support replacing sump pumps Verify system response following cleaning activities I
I 14 i
Degraded RF System - cont.
~
Corrective Actions - cont. -
- Other RF System Activities ,
Submitted Training Revision Request 97-952 to review operator training package on RF system.
Submitted Preventive Maintenance program change, Loe !
Number 97-117, to add PM activity.to boroscope the Flow Control Device at outage completion and as a final step in hydrolazing activities of RF drains.
Submitted Drawing Change Request (DCR 970069) to change drawings accordingly to identify the flow control box Revised Containment loose debris surveillance and RCFC monthly surveillance procedures 15
Prior Opportunity To Identify
~
L Operztor response to indications :
RF008
- Recorder .
- Alarm 16
Normal and Historical RF008 Response
~
Recorder changes
- performing containment release
- performing RCFC surveillance ~
- restricted weir
- steam generator secondary side leakage Alarms responded as expected during this perioc.
i 17
t Operator Response To Alarm -
Byron Annunciator Response Procedure
- Determine leak location
- Verify redundant indications sump pump run times radiation monitors Volume Control Tank (VCT) level Containment pressure
- Perform R.eactor Coolant System Water Inventory Balance 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> surveillance (BOS 4.6.2.1.d-1).
- Perform Containment Floor Drain Monitoring System ,
Non Routine Surveillance (BOS RF-1) .
18 ,
i I
Operator Response To Alarm - cont,
~
BOS RF-1
- Used if alarm in.without corresponding RCS leakage
- Look at RF sump level changes over time, RCS leak '
. rate
- Calculates new limits for baseline data
- Monitors RF008 every 30 minutes 19
~
e 2RF008 Reasonable Opportunity to Identify
- 2RF008 recorder Located behind the Main Control Board
- Qualification not quantification Good trend indicator Nuclear Station Operator must be relieved to check 1 gpm leak easily detectable on the VCT level recorder Leak detection alarm indicates >l gpm increase Recorder checked at least once per shift 20
, _ ___ ____ _ l
T Operators Opportunity To Identify System Problems
- Recorder and alarm alerted operators to changing
.ea(age Operators verified indications with redundant !
indications or procedures Operators wrote PIFs when input changes were
- verified Operators verified containment status monthly during performance of the RCFC surveillance When alarms were received, operators responc ed per procedures Operators took actions to verify RCS leakage eaca time an alarm was ac clowledged
. . _ _ - _ _ _L
l l LER Quality I
Findings .
- Containment floor drain system not declared inoperable
- Information not considered complete and accurate ;
- Safety Analysis was considered weak G
l 22 -
l
LER Quality - cont.
l l
' Corrective Actions
- Implementing collegial Plant Operating Review Committee (PORC)
LERs will be reviewed by PORC
- Training sessions with major OSR reviewers and Root Cause. Experts
- Submit supplemental LER 23
m - A a-e e !
)
f
)
m ,
1 l
4 Z .
O GO C ,
hiM U
Z O
U 4
i l
- _ _ ._ __-. _