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: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
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e Commonwealth Edmm Oimpan)
Ilyron Generating Station 4450 Wrth Ucrman Church Road 9 pyron, lL 610in9794 Tel H15-2M54 il 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. Graesser dated 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 ano 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 contain, 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 acditional training on identifying contamination hazards.
- 2) In addition to establishing priorities for decontamination activities, the RP Department will also assist Operating in ,l initiating been tagged.action requests for leaking equipment which has not yet -l- ~
/
- 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. l }
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Byron Ltr. 97-0106 May 5, 1997 Page 2 l
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l If your staff has any questions or comments concerning this letter, please refer them to 9on Brindle, Regulatory Assurance Supervisor, at (815)234-5441 i ext.2280.
Respectfully, l
1 o (
)K. L. Gr as r l
. Site Vice P sident Byron Nuclear Power Station .
l KLG/DB/rp Attachment (s) cc: A. B. 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 Manager, Downers Grove Safety Revie Dept, c/o Document Control Desk, 3rd Floor, Downers Grove DCD-Licensing, Suite 400, Downers Grove.
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J VIOLATION (454/455-97003-02)
Technical Specification 6.8.l _ requires, in part, that written procedures shall be established,Jimplemented and maintained covering activitiosareferenced in I Appendix A of Regulatory C"ide 1.33, Revision 2, February 1978.
- a. Regulatory Guide 1.33, Appendix A recommends that radiation 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 centimeters (an ) be posted with a sign that states." CAUTION, 2
CONTAMINATEC AREA."
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 which contained removable. contamination of 1,000 to 6,000 dpm per 100 cm2 were not posted with a sign.that stated, " CAUTION, CONTAMINATED AREA." (50-454/97003-02a and 50-455/97003-02a)
- b. Regulatory Guide 1.33, Appendix A recommends that procedures be
. implemented which specify chemistry instructions and the 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 cubic centimeter gas vial be evacuated prior to containing a 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
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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 chendstry 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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REASON FOR THE VIOI.ATION
- a. Radiological Posting and Labeling Requirements (50-454/455 97003-02a)
Per BRP 5010-1, " Radiological Posting and Labeling Requirements", areas 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 4 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 surveys of these areas due to a lack of attention to detail. BRP 6020-3, " Routine Plant Surveys", requires contamination surveys of work surfaces, equipment, and floors to support general access. However, the contamination surveys were not performed in sufficient detail to identify the contamination on the pump seals. It was apparent that the pump seals had leaked primary system water which after evaporation, resulted in a collection of dried boron which is a known contamination hazard.
The Radiation Protection Department is connCtted to maintaining high material conditio: standards in radiologically posted areas to ensure i 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 housekeeping practices, radiological hazards are reduced and personnel contamination events are mini.ed/ed.
- b. Preparation of Gas Samples for Isotopic Analysis (50-454/455 97003-2b)
The set-up of instrumentation and analysis for a gas sample was being ,
performed by two (2) Chemistry technicians. The gas vial was not evacuated due to a miscommunication between the technicians. The status of the analysis activities was not properly maintained.
- c. Procedure Adherence Procedure (50-454/455 97003-2c)
Chemistry Department Policy 200-3 covers procedure acherence, 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.
CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED Individual corrective actions with regard to the llotice of Violation is as follows:
- a. Radiological Posting and Labeling Requirements (50-454/455 97003-02a)
- 1. To emphasize procedure compliance and material condition priorities, Radiation Protection management reviewed department expectations during continuing training sessions which concluded in March 1997. Fainted discussions on survey expectations focused on the importance of properly identifying and posting contamination hazards. All Radiation Protection Laboratory 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 l completed since management expectations were presented and no additional contaminated areas were found that were not posted,
- b. Preparation of'5+;> Samples for Isotopic Analysis (50-454/455 97003-2b)
- 1. The chemistry technicians were copnseled 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 samplir: procedures in i HRSS ha a been placed in plastic. covers and marking pens will be ,
used to : ark steps.
- c. Proc.edure Adherence' Procedure-(50-454/455 97003-2c)
- 1. None i
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' CORRECTIVii. MEPS 'THAT WILL BE TAKEN TO AVOID FURTHER VIOLATION '
- a. Radiological Posting and Labeling Requirements (50-454/455 97003-02a)
'l. To assist Radiation Protection (RP) in identifying contamination control concerns as conditions in the plant change between routine surveys, operating personnel will receive adattional. training on identifying contamination nazerds. 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 40norols are established. Training Revision Request ;
(TRR)97-810 will track this training.
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- 2. In addition to establishing priorities for decontamination activities, the RP Dept, will also assist Operating in initiating ,
action requests for leaking eqaipment which has not yet been .
tagged. This will also assist RP in reducing repeat-decontamination by ensuring the cause of the leak is. addressed.'
TRR 97-809 will track training RP on submitting action requests.
- b. Preparation of Gas Samples for Isotopic Analysis (50-454/455 97003-2b) !
.l. None P
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- c. Procedure Adherence Procedure (50-454/455 97003-2c) l.l To meet'Rev alatory Guide 1.33, Appendix A requirements,. Chemistry 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. .NTSN 454-100-97-00302c-01 tracks this action.
-DATE WHEN FULL CcMPLIANCE WILL BE ACHIEVED
- a. Radi" logical Posting and Labeling Requirements (50-454/.455 97003-02a)
Full compliance.was achieved on 3/4/97 when the proper boundaries and postings were placed around the affected areas.
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- b. Preparation of Gas Samples for Isotopic Analysis (50-454/455 97003-2b) ;
i Full compliance was achieved on 3/5/97 when the gas sample and analysis {
was performed.in'accordance with the proredure.
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'c. Procedure Adherence Procedure (50-454/455 97003-2c) 1 Full compliance will be. achieved by 8/29/97 when the procedure is I completed, approved for use, and site personnel have been trained. This issue was initially identified in the Chemistry area, training for .
' Chemistry personnel will be. completed by 7/15/97. ;
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VIOLATION (454/455-97003-04) , !
Technical Specification 6.8.4.d. requires that a program be implemented which will ensure the capability exists to obttin and analyze reactor coolant samples, radioactive iodine and particulate samples in plant gaseous effluents and conta'inment atmosphere samples under accident conditions.
Procedure BAP.560-10, " Byron Chemistry Post-Accident Program Description," Revision 2, dated December 2, 1996, requires, in part, that chemistry technicians receive semiannual training on the post accident sampling-system (PASS) and receive training on PASS procedures at least every six months.
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))
REASON FOR THE VIOLATION i
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 '
-changed to annually. BAP 560-10, " Byron Chemistry Post-Accident Program Description", was not revised to reflect the new requirements stated in BTP 300-29. '
b CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED
-1. BAP 560-10 was revised to clarify the requirements of PASS training for !
technicians.
- 2. Chemistry and Training personnel performed a review to assure that other >
training requirements are consistent between the, administrative and
. raining procedures. ;
CORRECTIVE STEPS THAT WILL BE TAKEN TO AVOID FURTHER VIOLATION .I
- 1. None DATE WHEN FULL CcNPLIANCE WILL BE ACHIEVED Full compliance was achieved on 4/29/97 with the completion of the revision to BAP 560-10.
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