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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Q>mmonw calth 1 dimn Company Ilyron Generating Station N** 4150 North German Church Road
, ' liyron, 11.610149791 Tel H15-245 4 41 May 1, 1997 LTR: EYRON 97-0105 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. 50-454/96013; 50-455/96013 l
NRC Docket Numbers 50-454, 50-455 l I
Reference:
Geoffrey E. Grant letter to Mr. Graesser dated March 31 1997, transmitting NRC Inspection
)
Report 50-454/96013; 50-455/96013 l Enclosed is Commonwealth Edison Company's response to the Notice of l Violation (NOV) and Unresolved Item (URI) which was transmitted with the referenced letter and Inspection Report. The NOV cited one (1) Severity Level IV violation requiring a written response. Comed's response is provided in the attachment.
We share your concern with repeat events occurring from ineffective i corrective actions. Byron Station has undertaken additional measures to assure that as deficiencies are identified, they are effectively corrected.
Examples of these actions includes:
Assignment of a senior management sponsor to all root cause investigations to remove barriers or challenges during the root cause investigations Establishment of Plant Operating Review Committee (PORC) by July 1, 1997 to review appropriate root cause investigations and related corrective actions.
I Additional staffing is being provided to the Root Cause -
Investigation Group to improve the quality of root cause #
O /
investigations. -
Cu.0069 9705060243 970501 '
PDR ADOCK 05000454. :
G PDR * ' ' ' * * * -
A 1.'nicom Company
Byron Ltr. 97-0105 May 1, 1997 Page 2 We also are concerned with the practice of allowing fire protection valves to remain in the as-left surveillance position for extended periods pending resumption of suspended surveillances. Operating will revise the appropriate procedures to preclude this practice.
In addition to the commitments stated above, this letter contains the following commitments relative to the Notice of Violation:
- 1. An Engineering Review will be conducted to ensure appropriate protective measures are installed to prevent future freezing of the instrument rack (0PL52J) in the Circulating Water Pump House (CWPH).
- 2. OBOS XFT-A1, " Freezing Temperature Equipment Protection", is being revised to include verification that the CWPH outside doors are adequately posted, warning that the doors are not to be propped open.
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
l
.( .-
K. L. G be er !
l Site Vice resident l Byron Nuclear Power Station I 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 Review Dept, c/o Document Control Desk, 3rd Floor, Downers Grove DCD-Licensing, Suite 400, Downers Grove. i I
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. i ATTACHMENT I VIOLATION (454/455-96013-02)
Criterion XVI, " Corrective Action," of 10 CFR Part 50, Appendix B, states, in i part, that measures shall be established to assure that conditions adverse to ;
quality are promptly identified and corrected. In the case of significant t conditions adverse to quality, the measure shall assure that the cause of the :
condition is determined and corrective action taken to preclude repetition. 4 i
Contrary to the above, as of March 10, 1997, the licensee failed to establish l effective corrective action to prevent recurring freezing of plant fire protection equipment during the previous and current winter seasons. :
t This is a Severity Level IV violation (Supplement I) (50-454/455/96013-02(DRS)).
i i
REASON FOR THE VIOLATION i
The Fire Protection lines noted were frozen for a variety of reasons: 1)outside ,
air dampers failed open; 2) cold temperatures in a warehouse; and 3)Various Circulating Water Pump House (CWPH) doors open for extended period of time. i On one occasion, the equipment doors were difficult to get closed after having ;
been open to transfer equipment. Before the doors could be closed, the sensing lines to the OA Fire Pump froze. This was unavoidable due to the cold i temperatures and location of the local panel OPL52J in relation to the doors. !
I On a second occasion, an individual's negligence to the sensitive nature of the plant equipment to adverse temperatures,.the door to the CWPH was propped open l resulting in freezing sensing lines to the 0A Fire Pump. The individual failed !
to practice attention to detail and think about how his action would affect the surrounding plant equipment.
The entrance doors to the CWPH are not classified as fire or security doors and they had no special labeling or warning signs posted to instruct personnel to special conditions.
CORRECTIVE STEPS TAKEN AND RESULTS ACHIEVED
- 1. .The OA Fire Pump sensing lines on local panel 0PL52J were thawed.
- 2. The CWPH doors were closed and work crew personnel were instructed not to block open the door.
- 3. A standdown was conducted at the start of the following two (2) shifts (days and afternoons) to assure personnel awareness of the incident.
- 4. Signs were ordered and placed at each entrance which state doors must remain closed at all times and cannot be propped open.
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1 l CORRECTIVE STEPS THAT WILL BE TAKEN TO AVOID FURTHER VIOLATION ,
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l 1. An Engineering Review will be conducted to ensure appropriate protective
) measures are installed to prevent future freezing of the instrument rack '
l~ (0PL52J) in the Circulating Water Pump House (CWPH) . This will be tracked j j by NTS #454-100-96-01302-01. .,i j 2. OBOS XFT-A1, " Freezing Temperature Equipment Protection", is being revised l to include verification that the CWPH outside doors are adequately posted, ~ t warning that the doors are not to be propped open. This will be tracked !
l by NTS #454-230-97-CAQS00009-02.
l 4
! DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED i Full compliance was achieved on 1/20/97 when repairs to the frozen instrument $
rack in the CWPH were completed. i
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, O ATTACHMENT II UNRESOLVED ITEM (454/455-96013-01) l PIF 4 54-200-96-0032, dated June 24, 1996, identified that all potential oil leaks on the reactor coolant pumps did not have drip pans to collect and route the oil to a safe collection point as required by 10 CFR 50, Appendix R.
The inspectors reviewed Byron Operability Assessment 96-025, dated June 25, 1996, and Byron RCP Oil Collection System Fire Protection Evaluation, dated June 24, 1996. The licensee's evaluation states, " Contrary to Byron's Fire Protection, Sections 3.7.G and A5.7.III.0, all potential oil leakage points are not provided with pans to collect drips and seepage. Specifically, there are two bolted i flanges and two drain plugs associated with the oil cooler on each RCP that were not initially provided with drip pans. " The licensee's evaluation also states, I
" Appendix R to Part 50 of Title 10 of the Code of Federal Regulations requires the installation of an oil collection system to collect cil from all potential pressurized and unpressurized leakage sites." However, the licensee determined it was acceptable to operate with this condition.
10 CFR 50, Appendix R, Section III, O, requires that RCP lube oil collecting systems shall he capable of collecting lube oil from all potential pressurized and unpressurized leakage sites in the RCP lube oil systems.
NUREG-0876, Safety Evaluation Report, Supplement No. 5, pages 9-17, closed an NRC unresolved issue identified in the Safety Evaluation Report regarding the provision of an oil collection system for the RCPs. This was based on the licensee's commitments in the fire protection report and letter dated August 20, 1984, to install an oil collection system capable of collecting oil from all
, potential pressurized and unpressurized leakage sites.
The Byron Fire Protection Report, pages 3.7-3 and AS.7-35, 36, stated that the l RCP lube oil leakage collection system complied with NRC and Appendix R requirements. PIF 454-200-96-0032 identified that the licensee was not in full l compliance. '
As corrective action to PIF 454-200-96-0032, the licensee installed additional drip pans under the bolted flanges and drain plugs and lengthened one drain pan.
Work had been completed on both units.
The licensee identified this issue and took appropriate corrective action. An operability Assessment was completed on July 25, 1996, that documented continued l operability of both units. However, the licensee was not in compliance with 10 CFR 50, Appendix R, Section O requirements since plant construction. I.
addition, the licensee failed to notify the NRC, pursuant to 10 CFR 50.73, that this condition was outside the Byron design basis, The licensee stated that the RCP oil collection system was not outside the Byron design basis and therefore was not reportable. This issue .a unresolved (50-454/455/96013-01(DRS)) pending review of the licensee's requested response to this issue.
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RESPONSE
10 CFR 50 Appendix R Subsection O (requirements for Reactor Coolant Pump (RCP) oil collection systems) requires that all leakage from pressurized and l unpressurized parts of the oil collection system be collected. Per our previous )
teleconferences regarding this issue, we feel that we are not outside our design basis for this system configuration. The reasons for this are as follows:
A response to question 600.1 of the Byron /Braidwood FSAR Amendment 47, dated April 1986 identified a discussion of conformance to 10CFR50 Appendix R and deviations f rom the requirements are described in Appendix AS.7 and A5.8 to the Byron /Braidwood FPR. Specifically, the deviation we submitted specified five (5) '
- drip pans on each RCP motor as described in the Fire Protection Report (FPR) on pages A5. 7-3 5 and A5. 7-36. The RCP motor oil drip pan installation as identified j was consistent with the original design. i 1
NUREG-0876, Safety Evaluation. Report, Supplement No. 5, pages 9-17, closed an NRC I j unresolved issue identified in the Safety Evaluation Report regarding the provision of an oil collection system for the RCPs. This was based on the licensee's commitments in the fire protection report and letter dated August 20, 1984, to install an oil collection system capable of collecting oil from all potential pressurized and unpressurized leakage sites. This document also states that "The system is designed and installed such that any failure will not lead to a fire during normal or design basis accident conditions, including safe shutdown earthquake. This commitment satisfies the guidelines contained in Section C.7.a of BTP CMEB 9.5-1 and is, therefore, acceptable."
This " acceptable condition" was furcher substantiated by NRC Inspection Report 83-62 in which the RCP Oil Collection system was reviewed and identified only a concern (Unresolved Item (URI) 50-454/83-62-37)with the oil holding tank collection capacity. This URI was subsequently closed, in NRC Inspection Report i 84-74, with no other concerns on the system.
The previous RCP oil collection configuration satisfies the intent of the system by preventing the anticipated leaks in both the high and low pressure portions of the RCP lube oil systems from coming in direct contact with potential ignition sources. In addition, the fire protection features provided in the containment structures are adequate to minimize potential fires, and the ability to achieve and maintain safe shutdown is not adversely affected by the previous configuration.
We were not outside our original design conditions. The new and revised drip pans were installed as an enhancement to our original design in the conservative direction.
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