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: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] |
Inspection Report - Byron - 1997003 |
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July 3, 1997 l
Mr. Site Vice President Byron Station Commonwealth Edison Company '
4450 N. German Church Road Byron, IL 61010
Dear Mr. Graesser:
l SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORTS 50-454/97003(DRS);
50-455/97003(DRS))
This will acknowledge receipt of your letter dated May 5,1997, in response to our letter dated April 4,1997, transmitting a Notice of Violation associated with activities at the Byron Generating Station, Units 1 and 2. The first violation contained in the Notice of Violation was associated with the failure to adequately implement chemistry and radiation protection procedures and to establish procedures which cover chemistry procedure usage. ,
We have reviewed your corrective actions for this violation and have no further questions '
at this time. These corrective actions will be examined during future inspections.
i However, we have questions regarding your response to the second violation contained in the Notice of Violation associated with the failure to c rain chemistry personnel on the post accident sampling system at a six-month frequency required by chemistry procedures. In your response, you stated that your staff revised the applicable procedure to clarify the training requirements. Through discussions with Mr. Robin Colglaizer of your staff, we understand that the procedure was revised to reduce the frequency of training from 6-months to 12-months. We are concerned that this change to your training requirements may not be consistent with previous commitments to the NRC.
In a January 5,1984, letter from T. R. Tramm of the Commonwealth Edison Company to H. R. Denton of the Office of Nuclear Reactor Regulation, commitments for periodic training and re-training of technicians on the post accident sampling system were ,
transmitted to the NRC. The letter indicated that training on procedures used to obtain }
post accident samples, which were not used in obtaining routine samples, would occur at least every 6 months. Subsequently, the NRC relied upon that information to evaluate the
})
,I adequacy of your post accident sampling capabilities. By our records, you have not notified the NRC of any intended change to the above commitment.
Based on the inconsistency between your proposed corrective actions and previous commitments to the NRC, we request that you evaluate your corrective actions and the above commitment to the NRC and submit an additional response within 30 days of the date of this letter addressing this inconsistency and providing additional information.
99 Ch llI.lli .lil.lil.lll.lll!.Ill.El.li 9707080405 970703 PDR ADOCK 05000454 G PDR
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If you have any questions concerning this request, please contact Mr. Steven Orth of my staff at (630) 829-9827.
Sincerely
.
Original Signed by Melvyn Leach (for)
John A. Grobe, Acting Director Division of Reactor Safety Docket Nos. 50-454; 50-455 Licenses Nos. NPF-37; NPF-66 Enclosures: 1. Ltr 05/05/97, K. L. Graesser, Comed, to US NRC 2. Ltr 01/05/84, T. R. Tramm, Comed, to US NRC cc w/o encis: T. J. Maiman, Senior Vice President, Nuclear Operations Division D. A. Sager, Vice President, Generation Support H. W. Keiser, Chief Nuclear Operating Officer K. Kofron, Station Manager D. Brindle, Regulatory Assurance Supervisor 1. Johnson, Acting Nuclear Regulatory Services Manager cc w/encls: Document Control Desk - Licensing Richard Hubbard Nathan Schloss, Economist Office of the Attorney General State Liaison Officer, Wisconsin State Liaison Officer Chairman, Illinois Commerce Commission Distribution:
Docket File w/encls Rlli PRR w/encls J. L. Caldwell, Rlll w/encls PUBLIC IE-01 w/encls SRis, Byron, Braidwood, Rlll Enf. Coordinator w/encls OC/LFDCB w/encls Zion w/encls R. A. Capra, NRR w/encls DRP w/encls LPM, NRR w/encis TSS w/encls DRS w/encls A. B. Beach, Rlli w/encls DOCDESK wencls DOCUMENT NAME:G:\DRS\BRYO70}7.DRS To receive a copy of this docurnent, indicate in the box: 'C' = Copy without attachrnent/enciczure "E" = Copy with attachrnent/ enclosure
- N* = No copy 0FFICE RIII le RIII c RIII l x) Rill [c NAME S0rth:jp # GShear 646 RLanskbury @ $ JGrobe #- 6 4--
DATE 07/l /97 07/ / /97 07/.3 /97 07/ 3 /97 Ott1C1AL RLCOMU CDPY
Commonw ealth 1.dmn Compan)
y lh run Generating station
. 4 450 North (scrnun (.hurch Road
lh run.1161010-9 91
TclH142 M 5441 May 5, 1997 LTR: BYRON 97-0106 FILE: 1.10.0101 U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk Subject: Byron Nuclear Power Station Units 1 and 2 Response to Notice of Violation Inspection Report No. 50-454/97003; 50-455/97003 NRC Docket Numbers 50-454, 50-455 Reference: Geoffrey E. Grant letter to Mr. Graescer dated ,
I April 4, 1997, transmitting NRC Inspection Report 50-454/97003; 50-455/97003 Enclosed is Commonwealth Edison Company's response to the Notice of Violation (NOV) which was transmitted with the referenced letter and Inspection Report. The NOV cited two (2) Severity Level IV violations requiring a written response. Comed's response is provided in the attachment.
This letter contains the following commitments:
1) To assist Radiation Protection (RP) in identifying contamination control concerns as conditions in the plant change between routine surveys, operating personnel will receive additional training on identifying contamination hazards.
2) In addition to establishing priorities for decontamination activities, the RP Department will also assist Operating in
, initiating action requests for leaking equipment whi;h has not yet l been tagged.
!
3) Chemistry personnel, along with Office Support, are developing a new procedure BAP 1310-10, " Procedure Use and Adherence" to address Regulatory Guide 1.33, Appendix A requirements.
.
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MAY 0 8 517, A I,nicom Compam ^
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! Byron Ltr. 97-0106 '
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May'5, 1997.
Page 2 i
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'If your staff has any questions or comments concerning this letter, please l refer them to Don Brindle, Regulatory Assurance Supervisor, at (815)234-5441 :
ext.2280. t
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Respectfully, d<)
'
,
l l- 3K. L. Gr ss l' Site Vice P sident l Byron' Nuclear Power Station !
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KLG/DB/rp -
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cc: A. Bs Beach / NRC Regional Administrator - RIII G. F.. Dick Jr.,. Byron Project Manager - NRR S. D.. Burgess, Senior.. Resident Inspector, Byron R. D. Lanksbury, Reactor Projects Chief - RIII '
F.'Niziolek, Division of Engineering - IDNS. ,
D. L. Farrar, Nuclear Regulatory . Services Mat ager, Downers Grove
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ATTACHNENT I VIOLATION (454/455-97003-02)
Technical Specification 6.8.1 requires, in part, that written procedures shall be established, implemented, and maintained covering activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. j i
Regulatory Guide 1.33, Appendix A recommends that radiation
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protection procedures be implemented which cover contamination control. -
Procedure BRP 5010-1 " Radiological Postings and Labeling Requirements," Revision 12, dated January 31, 1997, requires, in part, that areas with removable contamination greater than or ;
equal to 1000 disintegrations per minute (dpm) per 100 square. l centimeters ( cm ) be posted with a sign that states " CAUTION, a
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CONTAMINATED AREA."
I contrary to the above, as of March 3 and 4, 1997, areas within the 1A and 2A Chemical and volume Control System pump rooms, the 2A Safety Injection pump room, and the 2A Residual Heat Removal room j which contained removable contamination of 1,000 to 6,000 dpm per J 100 cm2 were not posted with a sign that stated, " CAUTION, ,
CONTAMINATED AREA." .(50-454/97003-02a and 50-455/97003-02a) l
b. Regulatory Guide 1.33, Appendix A recommends that procedures.be implemented which specify chemistry instructions and the j calibration of laboratory instruments.
Procedure BCP 300-62, " Preparation of Gas Samples for Isotopic ,
Analysis," Revision 4, dated November 14, 1996, requires that a 15 I cubic centimeter gas vial be evacuated prior to containing a i sample.
Contrary to the above, as of March 5, 1997, a chemistry technician failed to evacuate the gas vial prior to placing a sample in the vial. (50-454/97003-02b and 50-455/97003-02b)
c. Regulatory Guide 1.33, Appendix A recommends that procedures be established which cover procedure adherence.
Contrary to the above,.as of March 3, 1997, the licensee had not established procedures which cover adherence to chemistry g procedures. (50-454/97003-02c and 50-455/97003-02c). i This is'a Severity Level IV Violation (Supplement I).
(50-454/455-97003-02a, b, c(DRS))
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. i REASON FOR THE VIOLATION ,
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a. Radiological Posting and Labeling Requirements (50-454/455 97003-02a) ;
Per BRP 5010-1, " Radiological Posting and Labeling Requirements", areas l with removable contamination greater than 1000 dpm/100 cm are required
to be posted with a sign that states, " Caution Contaminated Area".
Contrary to this requirement, Radiation Protection did not post the 1/2A ;
Chemical and Volume Control (CV) Pumps, the 2A Safety Injection (SI)
Pump, and the 2A Residual Heat ~ Removal (RHR) Pump as contaminated areas.
Radiation Protection did not identify contamination on routine plant ,
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surveys of these areas due to a lack of attention to detail. BRP 6020-L 3, " Routine Plant Surveys", requires contamination surveys of. work {
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surfaces, equipment, and floors to support general access. However, the !
contamination surveys were not performed in sufficient detail'to J
- identify the contamination on the pump seals. It was apparent that the f pump seals had leaked primary system water which after evaporation,' l
! resulted in a collection of dried boron which is a known contamination l hazard.
The Radiation Protection Department is committed to maintaining high material condition standards in radiologically posted areas to ensure j
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minimal radiological impediments to safety related equipment. To !
achieve this goal, aggressive goals have been established for minimizing contaminated area square footage in the plant. By maintaining good ,
l housekeeping practices, radiological hazards are reduced and personnel. 1 l contamination events are minimized.
b. Preparation of Gas Samples for Isotopic Analysis (50-454/455 97003-2b) j I
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! The' set-up of instrumentation and analysis for.a gas sample was being '
performed by two (2) Chemistry technicians. The gas vial was not L evacuated due to a ndscommunication between the technicians. The status
! of the analysis activities was not properly maintained.
!J c. Procedure Adherence Procedure (50-454/455 97003-2c)
l Chemistry Department Policy.200-3~ covers procedure adherence,
. additionally Site Policy Memo 200-14 governs the use'of procedures.
Personnel had improperly relied on policies and memos in lieu of an approved procedure for providing guidance on-adherence'to procedures.
l CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED LIndividual corrective actions with regard to the Notice of Violation is as follows:
a. -Radiological Posting and Labeling Requirements (50-454/455 97003-02a) i 1. To emphasize procedure compliance and material condition
. priorities, ' Radiation Protection ' management . reviewed department expectations during continuing training sessions which concluded
. in March 1997. Pointed discussions on survey expectations focused
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on the importance of properly identifying and posting .
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contamination hazards. All Radiati'on Protection Laboratory
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. Supervisors and Technicians attended this training.
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2. All routine plant general area surveys as documented on BOP 6020-TB, "RP Lab Supervisor Routine Checklist", have been completed since management expectations were presented and no additional contaminated areas were found that were not posted.
b. Preparation of Gas Samples for Isotopic Analysis (50-454/455 97003-2b)
1. The chemistry technicians were counseled on the need for proper communication since they were involved in preparing the sample vial and did not communicate its actual status.
2. Preparation procedures in the Hot Lab and sampling procedures in HRSS have been placed in plastic covers and marking pens will be used to mark steps.
c. Procedure Adherence Procedure (50-454/455 97003-2c)
1. None CORRECTIVE STEPS THAT WILL BE TAIGN TO AVOID FURTHER VIOLATION a. Radiological Posting and Labeling Requirements (50-454/455 97003-02a)
1. To assist Radiation Protection (RP) in identifying contamination control concerns as conditions in the plant change between routine surveys, operating personnel will receive additional training on identifying contamination hazards. Operating has successfully identified equipment issues through the action request process in the past. Operating will now also notify RP when they identify adverse conditions, such as leaking equipment, to ensure proper radiological-controls are established. Training Revision Request (TRR)97-810 will track this training.
2. In addition to establishing priorities for decontamination activities, the RP Dept. will also assist Operating in initiating action requests for leaking equipment which has not yet been tagged. This will also assist RP in reducing' repeat decontamination by ensuring the cause of the leak is addressed.
TRP 97-809 will track training RP on submitting action requests.
b. Preparation of Gas Samples for Isotopic Analysis (50-454/455 97003-2b)
1. None
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c. Procedure Adherence Procedure (50-454/455 97003-2c)
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1. To meet Regulatory Guide 1.33, Appendix A requirements,. Chemistry I personnel, along with office Support personnel, are developing a procedure usage procedure. The new procedure BAP 1310-10,
" Procedure Use and Adherence", will be applicable to all Site
, personnel. NTS# 454-100-97-00302c-01 tracks this action.
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DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED '
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a. Radiological Posting and Labeling Requirements (50-454/455 97003-02a)
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Full compliance was achieved on 3/4/97 when the proper boundaries and '
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postings were placed around the affected areas. ;
J b. Preparation of Gas Samples for Isotopic Analysis (50-454/455 97003-2b)
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Full compliance was achieved on 3/5/97 when the gas sample and analysis was performed in accordance with the procedure. .
, c. Procedure Adherence Procedure (50-454/455 97003-2c)
J 4 Full compliance will be achieved by 8/29/97 when the procedure is completed, approved for use', and site personnel have been trained. This issue was initially identified in the Chemistry area, training for
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Chemistry personnel will be completed by 7/15/97.
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, e ATTACHMENT II '
VIOLATION (454/455-97003-04)
Technical Specification 6.8.4.d requires that a program be implemented which 4 will ensure the capability exists to obtain and analyze reactor coolant ,
samples, radioactive iodine and particulate samples in plant gaseous effluents i and containment atmosphere samples under accident conr'itions.
, Procedure BAP 560-10, " Byron Chemistry Post-Accident Program Description," Revision 2, dated December 2, 1996, requires, in part, j
, that chemistry technicians receive semiannual training on the. post accident sampling system (PASS) and receive training on PASS procedures at least every six months.
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Contrary to the above, PASS training of chemistry technicians was not conducted from October 1995 to June 1996, a period in excess of six months. (50-454/97003-04 and 50-455/97003-04)
This is a Severity Level IV violation (Supplement I). ,
(50-454/455-97003-04(DRP)) !
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REASON FOR THE VIOLATION In 1993, the Chemistry and Training Departments reviewed technician training for post-accident and revised the frequency as documented in Byron Letter 93-0312. Byron Training Procedure (BTP) 300-29, " Chemistry Department Training Program", was revised at the that time and the frequency of PASS training was I changed to annually. BAP 560-10, " Byron Chemistry Post-Accident Program l Description", was not revised to reflect the new requirements stated in BTP l-300-29. 1 l
l CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED 1. BAP 560-10 was revised to clarify the requirements of PASS training for technicians. .
l 2. Chemistry and Training personnel performed a review to assure that other training requirements are consistent between the administrative and training procedures.
CORRECTIVE STEPS THAT WILL BE TAKEN TO AVOID FURTHER VIOLATION
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1. None DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED
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Full d:ompliance was achieved on 4/29/97 with the completion of tihe revision to BAF 560-10.
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! ; .Y ;-n C:mm:nwealth Edison Ons hast Nahonal Plasa Checapo. In.no s
Address Reply solost Oif20 DDM 2 ! Chicago. Ithnois 60690 l January 5, 1984
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Mr. Harold R. Denton, Director
- Office of Nuclear Reactor Reculation U.S. Nuclear Regulatory Commission
{ Washington, DC 20555 i
l Subject Byron Generatlng Statlon Units 1 and 2
! Braidwood Generating Station Units 1 and 2
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Post Accident Sampling System NRC Docket Nos. 50-454, 50-455, 50-456 & 50-457 References (s): August 26, 1982 letter from T. R. Tramm to H. R. Denton.
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' (b): October 26, 1982 letter from T. R. Tramm to
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H. R. Denton.
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!; Osar Mr. Denton
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i This letter provides supplemental information regarding the i periodic training to be provided to Byron /Braldwood rad / chem technicians for post-accident sampling procedures. This revises information provided in reference (b).
t The Byron /Braldwood post-accident sampling system is the same
! sampling system used for routine sampling operations. Only a few special
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procedures are not used in obtaining and routine samples. The following special retralning will be completed by all radiation-chemistry j technicians at least every six months:
1. Review the following procedures BZP 380-10 " Post accident samplin of reactor coolant, redweste and containment air-genera .
BZP 380-11 " Post accident sampling of undiluted reactor coolant."
BZP 380-12 " Post accident sampling of diluted reactor coolant."
BZP 380-13 " Post accident sampling of undiluted liquid radwaste."
DZP 380-14 " Post accident sampling of diluted radweste."
BZP 380-15 " Stripped-gas sampling of post accident reactor coolant."
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- . 1 H. R. Denton -2- January 5, 1984
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i BZP 380-16 " Post accident diluted reactor coolant /radweste sample l disposal."
BZP 380-17 " Post accident sample transfer from primary sample room."
BZP 380-18 " Post accident sampling of containment atmosphere. room."
BZP 380-A7 " Post accident sample transport routes."
2. Perform or witness the performance of five of the ten procedures listed at the high radiation sampling system. Over the course of a year, all ten procedures must be performed or witnessed.
Please direct further questions regarding this matter to this office.
Very truly yours, fik&
T. R. Tramm Nuclear Licensing Administrator 1m l
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