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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Text
i Comnmnwralth likson Comruny l
Ily ron Generating Station
.'t 4 650 Nonh Gennan Church Road i I fly ron. lL 6lO149791 1cl H15 2M5161 l
l April 11, 1997 LTR: BYRON 97-0084 FILE: 1.10.0101 U.S. Nuclear Regulatory Commission i Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Byron Nuclear Power Station Units 1 and 2 Response to Notice of Violation ,
Inspection Report No. 50-454/96012; 50-455/96012 l NRC Docket Numbers 50-454, 50-455
REFERENCE:
J.L.Caldwell letter to Mr. Graesser dated )
March 13, 1997, transmitting NRC Inspection Report 50-454/96012; 50-455/96012 l
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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 three (3) Severity Level IV violations requiring a written response. Comed's response is provided in the attachment.
This letter contains the following commitments:
- 1. Conduct an evaluation of changing the BAP 1100-3 requirements.
- 2. Refresher training to be given to the Station Laborer personnel on watertight door requirements.
- 3. Consideration to be given to installing cameras inside the SX pump rooms to monitor the WE and WF pump room doors.
- 4. An UFSAR update will be submitted to include a statement to provide for alternate monitoring in circumstances where the alarm function on the containment sump is annunciated due to
!!cn-RCS sources.
t 9704210015 970411 DR ADOCK 050004 4 l1D t
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A Unicum Onmpany
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. Byron Ltr: 97-0084 l April 11, 1997 I Page 2 l l
l If your staff has any questions or comments concerning this letter, please refer them to Don Brindle, Regulatory Assurance Supervisor, at (815) 234-5441 ext. 2280.
Respectfully, l
K. L. Graesser Site Vice President l 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 I 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 Review Dept, c/o Document Control Desk, 3rd Floor, Downers Grove DCD-Licensing, Suite 400, Downers Grove.
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ATTACHMENT I VIOLATION (4 54 /4 5 5 - 9 6012 - 03 a/b) 10 CFR Part 50, Appendix B, Criterion XVI, " Corrective Action", requires, in part, that measures be established to assure that conditions adverse to quality, such as deficiencies, deviations, and nonconformances are promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is i determined and corrective action taken to preclude repetition. I
- a. Contrary to the above, on December 20, 1996, the inspectors I identified that corrective actions taken to preclude repetition of a previously discussed event were ineffective. Specifically, the l SI pump oil cooler end bell misalignment discovered on October 11, !
1995, was similar to the misalignment of the essential service water room cooler cooling water divider plates on December 20, 1996. Both events involved orientation of flow dividers, either end bells or divider plates, on safety-related equipment (50-4 54 /4 55- 96012-03a (DRP) ) .
- b. Contrary to the above, on January 9, 1997, the inspectors identified that corrective actions implemented on December 15, 1996, in response to NRC identified findings identified on February 22 and July 15, 1996, were ineffective. Adequate training was not given to appropriate maintenance personnel, to preclude leaving the B train essential service water pump room j watertight door unattended for more than 15 minutes without a '
proper barrier / fire protection system impairment permit j (50-454/455-96012-03b(DRP)), '
l This is a Severity Level IV violation (Supplement I) . i l
l REASON FOR THE VIOLATION
- a. The mechanic was aware of the LCOAR situation with the time involved to perform the essential service water (SX) activities. He also had the company photographer and System Technical Expert with a Quality control Inspector examining the components. With these outside distractions the mechanic did not pay attention to detail and follow the procedure to verify the alignment of the matchmarks, and assembled the baffle plates incorrectly. l
- b. Past practice associated with watertight doors allowed the doors to remain open when the room was occupied. This action had been in effect since Rev. 8 of BAP 1100-3 " Fire Protection Systems, Fire Rated Assemblies, '
Ventilation Seals, and Flood Seal Impairments" dated September 26, 1990.
The most recent revision to BAP 1100-3, " Fire Protection Systems, Fire Rated Assemblies, Ventilation Seals, and Flood Seal Impairments", is dated December 16, 1996. This revision changed the requirements to "any watertight door that needs to be open for greater than 15 minutes must have a Barrier / Fire Protection System Impairment Permit, BAP 1100-3T1".
Signage that reflects this procedure change was installed on all 10 watertight doors at the Station by October 14, 1996.
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The Mechanical Maintenance (KM) crew personnel interviewed did not notice any specific signage when performing work on the 1B SX Strainer.
Personnel had not been trained on the procedure which was revised in I December of 1996 and an NTS item was written to review new procedure with Maintenance personnel by March 28, 1997. The incident happened between 2
these two dates.
The cause of the event was inattention to detail and unawareness of a recent procedure change, which required an Fire Protection Impairment ;
Permit (FPIP) whenever the SX Pump Room door is to remain open for greater j than 15 minutes.
CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED
- a. Essential Service Water Room Cooler Cooling Water Divider Plates
- 1. Mechanical Maintenance personnel involved were coached on the importance of attention to detail, and procedure adherence in their 1 work.
- b. Watertight Door for Essential Service Water (SX) Pump Room Found Open
- 1. A Fire Protection Impairment Permit (FPIP) was written to allow the watertight door to be left open.
- 2. All Maintenance personnel discussed the event (open watertight door) at departmental safety meetings shortly after the event occurred and addressed the procedure change.
- 3. An Action Request (AR) #970025192 was written to change door signage to require closing of the door or obtain an FPIP.
- 4. Operations, Engineering, Radiation Protection, and Security department personnel received a required reading package discussing the event and the procedure change.
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, . . - . - . . _ . _ . _ . . ~ ~ . _ _ . , ~ . . . ~ _ . _ _ . . - _ . ~ ~ _ _ _ .
c CORRECTIVE STEPS THAT WILL BE TAKEN TO AVOID FURTHER VIOLATION
- a. Essential Service Water Room Cooler Cooling Water Divider Plates
- 1. None
- b. Watertight Door for Essential Service Water (SX) Pump Room Found Open
- 1. An'evaluationofchangingtheprocedurerequirementswilj.be I tracked in NTS by item #454-201-97-0068-01. j
- 2. Refresher training to be given to the Station Laborer personnel on watertight door requirements. This item will be tracked via NTS #454-201-97-0068-02.
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- 3. Consideration to be given to installing cameras inside the S7 ; pump i rooms to monitor the WE and WF pump room doore. The only I additional requirements that have been placed on thesa doort (4 I total) is the signage. One camera in each room would oe j sufficient to monitor both doors contained within that room. There currently is a camera system being evaluated that is monitoring the Diesel Oil Storage Tank Room doors and the A/B Train SX Pump Room doors. This item will be tracked via NTS #454-201-97-0068-05.
- DATE WHEN FULL COMPLIANCE WIT.L BE ACHIEVED
- a. Full compliance was achieved on 1/02/97 when the essential service water room cooler cooling water divider plates were reassembled in their correct configuration.
b, Full compliance was also achieved on 1/10/97 when a Fire Protection Impairment Permit (FPIP) was written to allow the B train essential service water pump room watertight door to remain open.
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4 ATTACHMENT II VIOLATION (454/455-96012-05) 10 CFR Part 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings ", requites activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the i circumstances and be accomplished in accordance with these instructions.
Byron Administrative Procedure 390-13, " Degraded Equipment Program", Revision 4, requires entries into the degraded equipment log for " inoperable subsystems or components of technical specification required equipment such that the function l of the corresponding TS equipment is not impaired but increased awareness is i deemed appropriate at the (operators) discretion."
- Contrary to the above, the inspectors identified that on December 29, 1996, the Unit 1 Containment Floor Drain system was not placed on the Degraded Equipment Log while the alarm was not able to perform its function to identify a reactor coolant system leak as designed, even though the chart recorder was operable and a procedure had been implemented to provide increased awareness (50-4 54 /455-96005 (DRP) )
This is a Severity Level IV violation (Supplement I).
REASON FOR THE VIOLATION i
The reason for the violation was a misinterpretation of the intent of BAP 390-13.
The Degraded Equipment Log (DEL) is used as a tool by the Unit Supervisors to assist them in determining if a component is in compliance with a Technical Specification.
A DEL entry should have been made due to the reliance on the 1RF000 recorder and log readings, per the procedure, to substitute for the alarm function. Failure ;
of this recorder would have resulted in a LCOAR entry, and should have been identified, via the DEL, as a protected item.
Since the contingency action directs the operator to use the 1RF008 recorder, and this action maintained the 1RF008 operable, the Unit Supervisor did not feel additional tracking for 1RF008 was warranted. This action was supported by the
" ope rators discretion" statement in BAP 390-13. However, the BAP also refers to equipment being " impaired". In this case, reliance on a contingency procedure to maintain operability met this criteria, and a DEL entry should have been made.
CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED
- 1. An entry into the DEL was made for the 1RF008.
- 2. The history, intent, and future purpose of the DEL was discussed at the March Unit Supervisors meeting.
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1 CORRECTIVE STEPS THAT WILL BE TAKEN TO AVOID FURTHER VIOLATION None DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance was achieved on 2/11/97 when the 1RF008 was entered into the I Degraded Equipment Log.
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ATTACHMENT III VIOLATION (454/455-96012-06) 10 CFR 50. 59 (b) (1) states that "The licensee shall maintain records of changes in the facility. . .to the extent that these changes constitute changes in facility as describe $ in the safety analysis report..." and "these records must include !
a written satety evaluation which provides the bases for the determination that the change, test, or experiment does not involve an unreviewed safety question" .
Contrary to the above, the inspectors identified that from December 29, 1996, ,
through December 31, 1996, a change in the facility as described in the Updated Final Safety Analysis Report was made without conducting a written safety evaluation. Specifically, the alarm function for the Unit 1 Containment Floor Drain (1RF008) was not available as described in the safety analysis report.
Operator action to log the flow rate into 1RF008 every one-half hour was implemented through an approved procedure without conducting a safety evaluation (50-4 54 /455-96012-06 (DRP) ) . ;
This is a Severity Level IV violation (Supplement I).
REASON FOR THE VIOIATION Once the alarm for 1RF008 was annunciated due to an increase in sump input from any source, further automatic warning to indicate a change in leakage from an RCS source is lost although the monitor remains capable of detecting / trending '
increases in containment sump input. By initiating procedure 1BOS RF-1, "ContalPhent Floor Drain Monitoring System Non-Routine Surveillance", the functiatul equivalent of an automatic alarm is restored such that the control i room operators will be alerted to an increase in leakage.
A 10 CFR 50.59 safety evaluation screening was performed on procedure 1BOS RF-1 with no discernable impact on the UFSAR. This was due to a misinterpretation of the alarm requirements as stated in the UFSAR.
CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED
- 1. A 50.59 safety evaluation was completed on 1/16/97 for 1BOS RF-1.
- 2. A copy of the 50.59 safety evaluation was forwarded to the appropriate Braidwood system engineer.
CORRECTIVE STEPS THAT WILL BE TAKEN TO AVOID FURTHER VIOLATION
- 1. An UFSAR update will be submitted to include a statement to say that in addition to the Main Control Rcom Alarm, Station procedures provide for l alternate monitoring in circumstances where the alarm function on the containment sump is annunciated due to Non-RCS sources. This action is tracked via 454-100-96-01206-01.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance was achieved on 1/16/97 when an appropriate 50.59 safety
[ evaluation was completed on 1RF008 and 1BOS RF-1.
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