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: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) ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes 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 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) 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 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 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 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) 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 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 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 ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs 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 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 ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20207E9831999-05-18018 May 1999 Forwards Copy of Commonwealth Edison Co EP Exercise Evaluation Objectives for 1999 Byron Station Annual EP Exercise,Which Will Be Conducted on 990825.Without Encl ML20206N8551999-05-11011 May 1999 Forwards 1998 Annual Radioactive Environ Operating Rept for Byron Station. Rept Includes Summary of Radiological Liquid & Gaseous Effluents & Solid Waste Released from Site ML20206U3351999-04-30030 April 1999 Forwards Evaluation of Matter Described in Re Byron Station.Concludes That Use of Overtime at Byron Station Was Controlled IAW Administrative Requirements & Mgt Expectations Established to Meet Overtime Requirement of TS ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206C7901999-04-23023 April 1999 Provides Suppl Info Re Use of W Dynamic Rod Worth Measurement Technique,As Requested During 990413 Telcon.Rev Bars in right-hand Margin Identify Changes from Info Submitted by ML20206E7521999-04-22022 April 1999 Submits Rept on Number of Tubes Plugged or Repaired During Inservice Insp Activities Conducted at Plant During Cycle 9 Refueling Outage,Per TS 5.6.9 ML20206A7431999-04-22022 April 1999 Forwards Comments Generated Based on Review of NRC Ltr Re Preliminary Accident Sequence Precursor Analysis for Byron Station,Unit 1 ML20206B3941999-04-21021 April 1999 Forwards Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors, for Byron & Braidwood Stations.Updated Info Re PCT for Limiting Small Break & Large Break LOCA Analysis Evaluations & Detailed Description of Errors ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205S9621999-04-20020 April 1999 Responds to 981203 RAI Telcon Re SG Tube Rupture Analysis for Byron Station,Unit 2 & Braidwood Station,Unit 2.Addl Info & Subsequent Resolution of Issues Discussed During 990211 Telcon Are Documented in Encl ML20206A8141999-04-20020 April 1999 Advises NRC of Review of Cycle 10 Reload Under Provisions of 10CFR50.59 & to Transmit COLR for Upcoming Cycle ML20205T3901999-04-13013 April 1999 Forwards Byron Station 1998 Occupational Radiation Exposure Rept, Which Is Tabulation of Station,Utility & Other Personnel Receiving Annual Deep Dose Equivalent of Less than 100 Mrem ML20196K6661999-03-31031 March 1999 Forwards Byron Nuclear Power Station 10CFR50.59 Summary Rept, Consisting of Descriptions & SE Summaries of Changes, Tests & Experiments.Rept Includes Changes Made to Features Fire Protection Program,Not Previously Presented to NRC ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207K0351999-03-0404 March 1999 Forwards Util Which Transmitted Corrected Pages to SG Replacement Outage Startup Rept.Subject Ltr Was Inadvertently Not Sent to NRC Dcd,As Required by 10CFR50.4 ML20205C6861999-03-0404 March 1999 Provides Notification That Byron Station Implemented ITS on 990205 & Braidwood Station Implemented ITS on 990219 ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207D4301999-02-26026 February 1999 Informs NRC That Supplemental Info for Byron & Braidwood Stations Will Be Delayed.All Mod Work Described in Ltr Is on Schedule,Per GL 96-06 ML20207B8971999-02-25025 February 1999 Expresses Concern That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazard at Some Commercial Nuclear Plants in Us ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List ML20202F5911999-01-29029 January 1999 Forwards Byron Unit 1 Cycle 9 COLR in ITS Format & W(Z) Function & Byron Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function. New COLR Format Has Addl Info Requirements ML20199E1611999-01-15015 January 1999 Forwards Response to 980902 RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. CE Endorses Industry Response to RAI as Submitted by NEI ML20199B7511999-01-0808 January 1999 Forwards Proprietary Versions of Epips,Including Rev 52 to Bzp 600-A1 & Rev 48 to Bzp 600-A4 & non-proprietary Version of Rev 52 to Bzp 600-A1 & Index.Proprietary Info Withheld 1999-09-30
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _.
Gammonwealth Ediwn Company 7o, ..t.. H} ron Generating Station 4 450 North Gernun Church Road Hyron, II. 6101m>~91 TcI MI5-2R5 4 41
?
February 15. 1995 U.S. Nuclear Regulatory Commission Washington. DC 20555 i Attention: Document Control Desk l
Subject:
Byron Nuclear Power Station Units 1 and 2 Response to Notice of Violation Inspection Report No. 50-454/94026: 50-455/94026 NRC Docket Numbers 50-454, 50-455
Reference:
John B. Martin letter to Mr. Wallace dated January 25. 1994, transmitting NRC Inspection Report 50-454/94026: 50-455/94026 Enclosed is Commonwealth Edison Com)any's response to the Notice of Violation (NOV) which was transmitted wit 1 the referenced letter and Inspection Report. The NOV cited a Severity Level III and Severity Level IV violation requiring a written response. Comed's response is provided in the attachment.
If your staff has any questions or comments concerning this letter. I please refer them to Don Brindle. Regulatory Assurance Supervisor, at l (815)234-5441 ext.2280.
1 Respectfully. ;
/
s.
wuen L. Graesser Site Vice President Byron Nuclear Power Station Attachment (s) !
I cc: J. B. Martin. NRC Regional Administrator - RIII G. F. Dick. Byron Project Manager - NRR H. Peterson Senior Resident Inspector. Byron L. F. Miller Jr. Reactor Projects Chief - RIII D. L. Farrar. Nuclear Regulatory Services Manager. Downers Grove Safety Review Dept c/o Document Control Desk. 3rd Floor. Downers Grove 9502290350 950215 PDR ADOCK 05000454 i Q PDR i
t
~ - - - - -
i; j l
3 , )
i ATTACHMENT I VIOLATION (454(455)/94026-01)
Technical Specification 6.2.b requires, in part. that while the unit is in Mode 1.
at least one licensed Senior Operator shall be in the control room.
10 CFR 50.54(m)(2)(iii) requires that when a nuclear power unit is in an operational mode other than cold shutdown or refueling, as defined by the unit's technical specifications, each licensee shall have a person holding a senior operator license for the nuclear power unit in the control room at all times.
Contrary to the .above on October 14, 1994, while Unit 2 was in Mode 1 (a mode other than cold shutdown or refueling), a person holding a senior operator license '
was not in the common dual unit control room for a period of 22 minutes.
This is a Severity Level III violation (Supplement I). '
REASON FOR THE VIOLATION !
On first shift, during the early morning of October 14, 1994. the Unit 2 Turbine Building Eguipment Attendant (EA) came to the Unit 2 SRO Shift Su)ervisor (SS) in !
the Shift Engineer (SE) Office requesting guidance for swapping t1e oil filter on l the 2B Feedwater Pump. The SS needed to talk to the Unit 2 NSO on an unrelated '
topic, so be told the EA to go to the Unit 2 desk and that he, the SS. would join ,
him in a moment. At about 0201 hrs. the SS entered the Control Room and joined '
the EA at the U2 Nuclear Station Operator (NS0) Desk intending to discuss the pending filter swap with the NSO and the EA.
The Station Control Room Engineer (SCRE) a)proached the U2 NSO Desk and asked the U2 SS to relieve him for a few minutes. T1e SS agreed and, after a turnover, the SS assumed the Command and Control duties of the Control Room Supervisor SRO.
This SS stated that he normally moves his security badge to a different location on his body when he is performing a relief for the SCRE. as an additional reminder of his Control Room Supervisor responsibilities. On this occasion. however, he forgot to move his badge. There is no policy or procedure that requires the Control Room Supervisor SRO to perform this action. The SCRE exited the Control Room at 0203 hrs leaving the SS in charge of the Control Room.
The SS then discussed the procedure for swapping the Feedwater Pump oil filter to the EA. When he had completed his explanation, the EA was still not comfortable with performing the filter swap alone. The SS was focusing on the EA's lack of confidence in performing the pending task and his role in helping the EA. During this conversation, the SS became so involved that he mentally reentered his normal role as an in-plant su)ervisor. The SS told the NSO that he w'.uld accompany the EA and hel) him with t1e task, a routine aart of his normal first line supervisory duties. T1e NSO was not aware that the Slift Supervisor had taken the SRO duty for the Control Room and therefore, he did not remind the SRO of his Control Room i Duties. i I
i l
L The SS did not remember at that moment that he had the responsibility as the SRO in the Control Room. Unfortunately. his Shift Su effect. He exited the Control Room at 0210 hrs,and pervisor instinctsthe accompanied came EA tointo the 426' Turbine Building to help swap the oil filter on the running FW pump. In no way at all were the SS's actions malicious or intentional.
During a phone conversation at ap3roximately 0230. the Unit 1 NSO was told that a Maintenance Foreman was going to 3e coming in to talk to the SCRE. The Unit 1 NSO commented to the other NS0s present that the SR0 was not in sight. On infrequent occasions the SRO is out of the line of sight of the unit panels for short periods of time, such as when checking the back panels, going to the copy machine, or to the printers. The NS0s had been involved with their duties, and were not immediately aware that there wasn't an SRO present in the Control Room. One of the extra NS0s performed a quick check behind the panels and determined that there was no SR0 present in the Control Room. The Center Desk NSO immediately called the SE office. When no one answered, the NSO called on the radio for an SRO to come to the Control Room. Three messages were transmitted in a short time (within a minute).
During his absence from the Control Room. the SS had been assisting the EA in swapping the Feedwater Pump oil filter. They had finished the job, but the SS was still in the )lant when the Center Desk NSO made his request over the radio. The SS realized wlat he had done, and immediately returned to the Control Room. The Shift Supervisor reentered the Control Room at 0232 hrs, after an absence of 22 minutes.
The other SRO Shift Supervisor (SS2) on duty that morning also heard the radio message, verified the message over the radio, and came to the Control Room.
entering at 0234 hrs, just after the other SS's return. Moments later, at 0237 hrs, the SCRE also returned from his plant tour. He then assumed the responsibility of the Control Room Supervisor SRO.
At no time during this incident did a transient or accident occur. Unit 1 was in Mode 6 and Unit 2 was in Mode 1. steady state and stable throughout the period that the SRO was absent from the Control Room.
CORRECTIVE STEPS THAT HAVE BEEN TAKEN TO AVOID FURTHER VIOLATION e Placed a physical barrier to prevent the duty SR0 from leaving the Main Control Room. Developed a clasp to remind wearer of SRO responsibilities.
e Communicated the event and our expectations to all our operators in the form of daily orders.
e Revised Policies for the Operations Department Log entries and turnover items (BAP 350-1)
. Control Room announcements on who is in charge after a turnover (BAP
, 335-1) l
. How to conduct a mid-shift turnover (BAP 300-1. 335-1)
L . Notifications to management (Operating Policy 400-16)
. Morning phone message on plant operations (Operating Policy 600-1)
. Notifications both inside and outside the company (Operating Policy 400-16)
. Minimum manning requirements (BAP 320-1) l l
t
e Both the SE and the SS received counselling on 10/19/94 in addition to '
disciplinary action. 1 e Shift Engineers were assigned the task of re-focusing on their 1 responsibilities and developed the Shift Engineer Mission Statement of responsibilities.
I e In addition, not as a result of this event but accelerated because of it, we l assigned the Operations Self Assessment Committee to lonk at all of the {
shift operations and have implemented the following recommendations: !
. Two SRO's assigned to the Control Room. SCRE will be single point of '
accountability. He will be relieved of Administrative duties and will maintain his overview function.
Rules of conduct for the SR0 turnover in the Main Control Room.
l . Relieving the shift operators of some of their administrative burden
[ to enhance focus on unit operations
. Operating Management, who work outside of the MCR. directly reporting to the Shift Engineer will work out of the Shift Engineer's office.
. Reinforce the " quiet time" for MCR Turnovers and enhance the Shift Briefing protocol.
- Reviewed the Training Lesson Plan regarding Tech Spec Section 6.
Highlighted those Specs that were pertinent to Licensed Operators on shift.
This training was completed during the first cycle of licensed operator training in 1995.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance was achieved when the SRO returned to the control room 10/14/94 at 0232 hrs.
r f
f i
ATTACHMENT II VIOLATION (454(455)/94026-02) i Technical Specification 6.8.1 requires that written orocedures recommended in Appendix A of Regulatory Guide 1.33 . Revision 2. Fearuary 1978. be established and implemented. Regulatory Guide 1.33 requires administrative procedures addressing log entries.
Byron Administrative Procedure (BAP) 300-1. Conduct of Operations. Revision 11 Section C.5.a. a) proved March 7. 1994. requires that shift records be kept in accordance with 3AP 350-1.
BAP 350-1. Operating Logs and Records. Revision 6. Section C.2.f. approved March
- 7. 1994, requires that the Shift Engineer's Log should contain potential reportable occurrences.
Contrary to the above. on October 14. 1994, the Shift Engineer's Log did not contain an entry for not having a licensed senior operator in the control room for 22 minutes while Unit 2 was in Mode 1 which is reportable per 10 CFR 50.73(a)(2)(1)(B).
This is a Severity Level IV violation (Supplement I).
REASON FOR THE VIOLATION The SE & SS knew of a requirement for an SRO in the Control Room and reviewed Tech Specs for applicability. Looking at Tech Spec Table 6.2-1, titled Minimum Shift Crew Composition the SE and the SS decided that although there was some question whether or not minimum manning had been maintained (per paragraph 2 Table 6.2-1) the requirement was now satisfied and there was no sense of urgency to write a PIF.
Since it was now late in the shift the SE decided to continue his investigation the next day at 1800. The next evening further clarification was found in Tech Spec 6.2.2. Returning to work later that evening (Friday night for Saturday.
October 15. first shift) were two of the NS0's from the previous night. After the 2300 shift briefing an SS informed the SE that the NSO's from the previous night were discussing the matter of the SRO leaving the MCR with the new NS0's. The SE went into the MCR on Unit I and questioned them about the matter asking who noticed that the SRO was gone, what prompted them to notice & why did it take so long to notice. Away from the main conversation an NSO asked the SE how high had this gone and the SE replied that so far he was the only one but that the Ops Manager would be informed later that night when he came in to support an outage appreciation event at 3 AM. The SE then called Security and requested door 1 records for the MCR. After reviewing those records it was determined that the I absence was 22 minutes and that there was no other SRO in the MCR at that time. I The PIF was then written. Although the SE realized that a Tech Spec requirement l had not been met he did not realize at the time that it was outside the bounds of ;
the Tech Spec and therefore did not make any further notification or log it. !
CORRECTIVE STEPS THAT HAVE BEEN TAKEN TO AVOID FURTHER VIOLATION e Emphasized use of logs and turnovers as a communications tool and as a legal document concern.
e Emphasized writing PIFs on all identified problems with content consistent with management expectations.
- Emphasized the importance of concise communications within the Department.
e Counseled the SE and SS regarding their responsibilities.
e Reviewed the Training Lesson Plan regarding Tech Spec Section 6.
Highlighted those Specs that were pertinent to Licensed Operators on shift.
This training was completed during the first cycle of licensed operator training in 1995.
e Developed Computerized Turnovers to enhance documentation and upper management review of such.
e Revised Policies for the Operations Department Log entries and turnover items (BAP 350-1)
. Control Room announcements on who is in charge after a turnover (BAP 335-1)
. How to conduct a mid-shift turnover (BAP 300-1, 335-1)
. Notifications to management (Operating Policy 400-16)
. Morning phone message on plant operations (Operating Policy 600-1)
. Notifications both inside and outside the company (Operating Policy 400-16)
. Minimum manning requirements (BAP 320-1)
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance has been achieved.
!