|
|---|
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)
ML20217M4361999-10-19019 October 1999
Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21
ML20217H4661999-10-18018 October 1999
Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl
ML20217G9791999-10-14014 October 1999
Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2
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
ML20217A9311999-09-29029 September 1999
Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem
ML20216H4301999-09-23023 September 1999
Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108
ML20216F7441999-09-17017 September 1999
Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424
ML20212A6991999-09-10010 September 1999
Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2
ML20211Q9011999-09-0808 September 1999
Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed
ML20211Q6611999-09-0606 September 1999
Informs That NRC Tentatively Scheduled Initial Licensing Exam for Braidwood Operator License Applicants During Wk of 010115 & 22.Validation of Exam Will Occur at Station During Wk of 001218
ML20211P1901999-09-0303 September 1999
Forwards Insp Repts 50-456/99-12 & 50-457/99-12 on 990707-0816.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls
ML20211P1761999-09-0202 September 1999
Discusses Licensee Aug 1998 Rev 3K to Portions of Braidwood Nuclear Power Station Generating Stations Emergency Plan Site Annex Submitted Under Provisions of 10CFR50.54(q). NRC Approval Not Required
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
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)
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
BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999
Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2
BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999
Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station
ML20210N5651999-08-0606 August 1999
Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes
ML20210U8031999-08-0404 August 1999
Forwards SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval for Second 10-year Inservice Testing Program
BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999
Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle
ML20210M9131999-08-0202 August 1999
Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed
ML20210K9761999-07-30030 July 1999
Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs, for Plant
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
ML20210G6291999-07-29029 July 1999
Forwards Insp Repts 50-456/99-11 & 50-457/99-11 on 990525-0706.Two Violations Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy
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..
BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999
Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr
ML20216D3781999-07-21021 July 1999
Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA
ML20210C3961999-07-20020 July 1999
Forwards Insp Repts 50-456/99-09 & 50-457/99-09 on 990517-0623.No Violations Noted.Weakness Identified on 990523,when Station Supervisors Identified Individual Sleeping in Cable Tray in RCA
ML20216D7061999-07-19019 July 1999
Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21
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)
BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999
Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7
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
IR 05000456/19993011999-07-15015 July 1999
Forwards Operator Licensing Exam Repts 50-456/99-301OL & 50-457/99-301OL for Test Administered from 990607-11 to Applicants for Operating Licenses.Three Out of Four Applicants Passed Exams
BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999
Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted
ML20209H5141999-07-14014 July 1999
Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Braidwood Nuclear Generating Station for Week of 990927,which Coincides with Licensee Regularly Scheduled Exam Cycle
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
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
ML20196H0631999-06-28028 June 1999
Provides Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls
ML20212H8241999-06-24024 June 1999
Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick
ML20196D4591999-06-18018 June 1999
Forwards Insp Repts 50-456/99-07 & 50-457/99-07 on 990414- 0524.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices
ML20196A6671999-06-17017 June 1999
Refers to 990609 Meeting with Util in Braidwood,Il Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff
05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999
Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below
05000456/LER-1998-004, Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations1999-06-16016 June 1999
Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations
05000456/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed1999-06-15015 June 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed
ML20195J3741999-06-14014 June 1999
Forwards Insp Rept 50-457/99-08 on 990415-0518.No Violations Noted.Sg Insp Program Found to Be Thorough & Conservative
BW990028, Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.51999-06-10010 June 1999
Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.5
ML20195F3231999-06-0909 June 1999
Informs That in ,Arrangements Finalized for Exam to Be Administered at Plant During Wk of 990607.All Parts of Plant Initial Licensed Operator Exam Approved for Administration
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)
ML20217M4361999-10-19019 October 1999
Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21
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
ML20211Q9011999-09-0808 September 1999
Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed
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)
BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999
Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2
BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999
Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station
ML20210N5651999-08-0606 August 1999
Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes
BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999
Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle
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..
BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999
Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr
ML20216D3781999-07-21021 July 1999
Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA
ML20216D7061999-07-19019 July 1999
Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21
BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999
Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7
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
BW990040, Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted1999-07-15015 July 1999
Forwards Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2.Since Issuance of Rept,It Was Determined That Rt That Occurred on Unit 2 During Startup Was Inadvertently Omitted
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
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
05000457/LER-1998-003, Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below1999-06-16016 June 1999
Forwards LER 98-003-00 Re Unit 2 Reactor Trip.Actions & Associated Action Tracking Number That Braidwood Station Is Committed to Implement in Response to LER Described Below
05000456/LER-1998-004, Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations1999-06-16016 June 1999
Forwards LER 98-004-01,IAW 10CFR50.73(a)(2)(i)(B). LER 98-004 Included Commitment to Transmit Supplemental Rept by 990628,due to on-going Evaluations
05000456/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed1999-06-15015 June 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B). Description of Action & Associated Action Request Number That Braidwood Station Is Committed to Implement Is Response to LER Is Listed
BW990028, Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.51999-06-10010 June 1999
Forwards Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function, IAW TS 5.6.5
ML20195E3451999-06-0707 June 1999
Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data
ML20195D6351999-06-0404 June 1999
Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs
05000457/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Listed1999-05-21021 May 1999
Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are 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
ML20206T3351999-05-17017 May 1999
Provides Written follow-up of Request for NOED Re Extension of Shutdown Requirement of TS Limiting Condition for Operation 3.0.3.Page 9 of 9 of Incoming Submittal Not Included
ML20206N7861999-05-14014 May 1999
Forwards 1998 Annual Radiological Environ Operating Rept for Braidwood Station. Rept Contains Info Associated with Stations Radiological Environ & Meteorological Monitoring Programs
ML20206Q8521999-05-13013 May 1999
Submits Rept on Numbers of Tubes Plugged or Repaired During SG Inservice Insp Activities Conducted During Plant Seventh Refueling outage,A2R07,per TS 5.6.9
ML20210C7221999-05-0303 May 1999
Forwards Initial License Exam Matls for Review & Approval. Exam Scheduled for Wk of 990607
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
ML20206E3991999-04-29029 April 1999
Forwards 1998 Annual Environ Operating Rept & Listed Attachments Included in Rept.Without Encls
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
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
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
ML20206B0821999-04-20020 April 1999
Requests to Reschedule Breaker Maint Insp for Either Wk of 990607 or One of Last Two Wks in Jul 1999,in Order to Better Accommodate Insp Activity
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
ML20206B0251999-04-14014 April 1999
Forwards Reg Guide 1.16 Rept for Number of Personnel & Person-Rem by Work Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions
ML20205K3581999-04-0606 April 1999
Submits Request to Reschedule Breaker Maint Insp for Braidwood Nuclear Power Station for Either Wk of 990607 or One of Last Two Wks in Jul 1999
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)
ML20210C7181999-03-30030 March 1999
Forwards Integrated Exam Outline Which Plant Submitting for Review,Comment & Approval for Initial License Exam Scheduled for Wk of 990607
ML20205E6401999-03-26026 March 1999
Forwards Proprietary Ltr Re Notification of Corrected Dose Rept for One Individual,Per 1997 Annual Dose Repts for All Comed Nuclear Power Facilities,Submitted 970430.Proprietary Info Withheld
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
ML20207J4321999-03-0808 March 1999
Forwards Braidwood Station ISI Outage Rept for A1R07, Per Requirements of ASME Section Xi,Article IWA-6200
ML20205C6861999-03-0404 March 1999
Provides Notification That Byron Station Implemented ITS on 990205 & Braidwood Station Implemented ITS on 990219
1999-09-08
[Table view] |
Text
_, .- .. - - . .
-i
'/ ^ CommonwrIth Edison
! - - Braldwood Nucitr Pour St; tion
.f 2_ Rout) 61, Box 84 b> Braceville, Illinois 60407 j Telephone 815/458-2801 '
I I
- February 24, 1995 j BW/95-0024 !
1 1
U. S. Nuclear Regulatory Commission !
Document Control Desk l Washington, D.C. 20555 j j
Subject:
Braidwood Station Unit Nos. 1 and 2 i Primary Coolant Specific Activity Annual Report d
-Docket Nos. STN 50-456 and STN 50-457
References:
. (a) NUREG-1276, Technical Specifications, ;
Braidwood Station, Unit Nos. 1.and 2 J l
Pur'suant to Specification 6.9.1.5.b'of' reference (a) the enclosures to this letter provide the analysis for.each occurrence in whi~' the primary coolant specific' activity.
exceeded the lir .3 of Specification'3.4.8 of reference (a) for Braidwood' Station during. calendar year-.1994. !
Please direct any questions regarding..this submittal to Doug Huston, Braidwood Licensing Coordinator,' (815) 458-2801, . !
extension 2511. I Yours truly, M
K. L. Kofron 7s&g~
Station Manager Braidwood Nuclear Station KLK/NS Enclosures (4) cc: J. B. Martin, Regional Administrator, Region III-S. G. DuPont, Senior Resident Inspector --Braidwood R. R. Assa, Braidwood Project Manager - NRR 000033
- I
/ f' ]
n:\correso\zcsteno. ,
l' 9503060061 950224 PDR. ADOCK 05000456-1 P PDR
I' f.
l 1'
ENCLOSURE 1-Braidwood Unit 1 i Primary Coolant Specific Activity Analyses I There were no occurrences during 1994.in which the.: primary- I coolant specific activity exceeded the limits of. Technical j Specification 3.4.8.
1 l .
? ,
l t
t l
l l
i
\
l i
o:\corresp\zcsteno 1 i
1 i
l ENCLOSURE 2 Braidwood Unit 2 !
Primary Coolant Specific Activity. Analyses I l There was one occurrence during 1994 in which the primary , 1 coolant. specific activity exceeded the. limits of Technical l Specification 3.4.8. The first sample exceeding the limit ;
occurred at 1835 on April 5, 1994, following a reactor' trip <
! approximately three hours earlier. The total time duration )
~
i when the specific activity of the primary coolant exceeded.the radioiodine limit was 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> and 40 minutes. l Enclosure 3 to this report contains Braidwood Unit 2 Power I History Hourly. Surveillance (2BwOS NR-1) for the.48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> l prior to the first sample exceeding-the specification limit.
i Enclosure 4-to this report.is a graph of results of the last j isotopic analysis for radiciodine performed prior to exceeding !
the limit, including results of analyses while exceeding the.
limit and analyses results after radioactivity was reduced to .
less than the limit. Also contained on the graph are other l radiciodine isotope concentrations in microcuries per gram as <
a function of time for the duration of thel specific activity I above the steady-state level, and sample results following retu;n to less than the specification limit. A chart is included with this enclosure detailing specific sample results !
versus reactor power and clean up system flow. . 1 l
o:\corresp\zcsteno 2 '
1 i
l i
l , i i -
i :
I ENCLOSURE 3 Braidwood Unit 2
! Power History Surveillance, 2BwCS NR-1 i
I i
b l
l l
l
\
i i
1 i
l l
o:\corresp\zesteno 3 l
Reviziro 2 INIIT' TWO PONER HISTOEr NOURIX WRVEILLANCE DATA SEEET DATE FOR NEICH THIS SURVEILLANCE IS BRING PERFORMED: / / I
'rw' AVG NUCLEAR 'r = AVG NUCLEAR inwar- Aerttir. pours carrytrf Tvm e. AerT1Ar. pmers carrytyr 0100 gjg y 7, Z, % m 1305 900 gTj %m
/M 0 00 yLg 7, C =P 1400 l'/c0 90J % RTP 0300 pfpo [ ] h % RTP 1500 fggpo [0, f % RTP
,f%RTP 0400 p Ap' 1600' /t.eo 1/, / - % RTP
!. 0500' [ p [ [, [ % RTP 1700 s 700 ' 92 / .% ITP b1 f600 QW W, f % m 1800 ; COO- 92.4. %m i 0700 o7e $C ( % nP 1m /qoo qf 9- %m O800 of50 ff, 1 % RTP 2000 moo 9:79 % RTP 0900 #fdC { {,2 % RTP 2100 9 / OO Y.I,' 3 % RTP
]
1000 goo p p,(, 4m 2200 Jaco f 3. 7 % m
} l
}
1100 ffog g, p ' % RTP '2300 2'5 eo' ff,2 - % m
- 1200 fg f,y ,% RTP .2400- hg . p . % RTP j i '
i f TOTAL POWER FOR THE DAY: M 7 7' (Total of each recorded hourly average Nuclear Power Output) l TOTAL EFPH FOR THE DAY: O O* 7 b (Total Power for the day' i l multiplied by 94) ;
PREVIOUS CUNULATIVE EFPR - /7 (Total EFPN to date from previous last run of this l; . surveillance)
EFPR ADJUSTMENT *** Signatures j TOTAL EFPR TO DATE: 7/ b " Y23 (TRANSFER to acat day's' i' earveillance or next rue of this surveillance)
I
{' D " INFO CNLY" copy placed la file (Reviewee).
l
)
- ** NAT WLY BE MADE AND SIGNED BY THE. STATICRI NUCLEAR ENGINEER OR 1 DESIGNEE. A WRITTEN DESCRIPTION OF THE REA8CRl(S) FOR THE ADJUSTMENT MUST BE ATTACBED.
(Final) A PPR OVE[.
il D-2 1 70(021793)/2 !dAR 171993 1 ZW2BMOS
~*?a?r?v?
]
1 i
4
. _ _ _ _ _ _ ~ _ . . -_ _ _. ~. .
+
2BwCE NR-1 4 Revision 2
.{
WIT TWO I'
- I POWER RIS M BOURLY SU NEILLANCE
- . ;; =.,.
DATE FOR WHICE TRIS SURVEILLANCE IS BEINtl PERFOMED:
/ ,
/,'- -
i
'YM AVG NUCLEAR vw AVG NUCLEAR'
[ '. v ne ar. - weesar. pe=re arrMrr rnear. - w=rivir. ,.u; m m,rr l-
'fgoo. 91.4 sm j oloo ojoo 952. sew 1n im 140o /h6 '9[, y sm 0200 61** ff,7 t
0300 .g 3,o 7(f. /_ 4 RTP 1500_ j if. f . s' RTF
! 0400 04o6- 9(p. It s RTP - 16o0 1/(g .f[ k T RTP 0500- U,O .s RTP 1700- (-)ov - - W.6 -s'RTP
- ~0500 ~
f
'Q,h (ga0 N'/'s'RTF
~
0600> s RTF 180o l go 0700 v7n - 9 7, o - s RTP 19oo gqe.o K 7 s RTP i
! 0s00 h'fDh 'gg,3 sm' 2000 2,oeo 'qq,7-s m !
d I 0900 070 0 $( % Err- 210e .y- .gq,g s RTP ]
M. 0 .s KTF '22o0' ;g g qdl,7'%RTP 1000 /00b i 1100 jiva 99. 7 s RTr 23oo ' ;y 'ff.7N m 1200 [g() %,h s RTP 2400' gp. % /..% RTP t
TUTAL POWER FOR TEE DAYS M [eb. (Total of each recorded. hourly ,
average Nuclear Power Output)
I 3
TOTAL EFPR FOR THE DAYS N' (Total Power for the day a
semitiplied by 9.J1)
PREVIOUS CUMULATIVE EFPRs Nbb (Total EFFR to date freni previous last ruc of this
! survellicace) 1 I'
1 EFFR ADJUS7 MENT **
Signatures 1
TOTAL EFFE TO DATE:
- 1) /O Ok1 (TRANSFER to next day's surveillance or mest run of j
this. surveillance)
I l' D " INFO CalLT" copy placed la file '(Reviewer).
l
- MAY (EfLT BE MADE AND SIGNED BT THE STATIN NUCLEAR ENGINEER OR '
) DESIGifEE. A WRITTEN DESCRIPTIN OF TEE REASON (S) FOR THE. ADJUSTMENT MUST BE ATTACRED.
f APPROVEC.
I D-2 -
70(o21793)/2 MAR 171993.
I IW2BN05 ~b?r*,?.*
h
! .,_,,.o,b,.m...,y
, , _ _ , _ . . .,,._,-.,e
Revicion 2 1
WIT TWO !
PONER BIETORY BOURLY WEVEZLLANCE DATA SEEET k / I/ N
~
DATE FOR NEICH TEIR SURVEILLANCE IS BEING PERFORMEDs
)
TM AVG NUCLEAR Tw AVG NUCLEAR rneir. Acmar. g 2; m,y vnear -- memar. pres == atrrstrr 0100 j/gp . h .7 % RTP 1300 l300 fk[%RTP 0200 Qg- %,}.~gRTP- 1400 )40 I b* % RTP .
0300- 83@ Q 9,7 % RTP 1500 l[6 O % 0), g . % RTP j 0400 @g)O ,7 % RTP 1600 p A. yf .% RTP 0500 /Jgoo %h % RTP 1700.. y4 g % RTP yf '% RTP 0600 hd# 'Cf { h % RTP 1800 - p4 gf % RTP 0700 07gpo .f g g g RTP 1900 g 0800i Ogod 99. [ % RTP '2000 ph pA % RTP 0900 0900' 99. g % RTP 2100 y4 g % RTP j 1000' /000 q q, [ % RTP '2200 d 'p k % RTP 1100 //8/)' ff, [ % RTP 2300 gg g% % RTP l
1200 / 20 Q- % [ % RTP 2400I p% pf % NT*
l i
TOTAL POWER FOR TEE.' DAY: 49tle (Total of each recorded hourly I average Nuclear Power Output) 1 TOTAL EFPH FOR THE DAY: 14.9 D (Total Power for the day j multiplied by 9.J11)
PREVIOUS CUNULATIVE EFPR 71/O.OT1 (Total'EFPR to date from j- previous last run of this.
i surveillance) 'f d
i EFPR ADJUSTMENT **t Signaturet TOTAL EFPR TO DATE.' 77 7 I O M '
- (TRANEFER to most day's
! surveillance or mest run of
[
0 " INFO ONLY" copy placed in file (Reviewer). l j ** MAY W LY BE MADE AND SIGNED BY THE STATIM NUCLEAR ENGINEER OR j DESIGNEE. A NRITTEN DESCRIPTIM OF THE REASW(S) FOR THE ADJUSTMENT j MUST BE ATTACBED.
h 7tgp A.T . \ $ 19 (Fir.al) APPROVEE ,
D-2 4 70(021793)/2 MAR 171993 EN2BNOS I 00N#,0,0 1-s 9
i
- 1. '
4, 4
ENCLOSURE 4 Braidwood Unit 2 i Isotopic Analyses of Radioiodines
~
Cleanup System Flow History 4
i l'
1-i
). f 1
1 4
4 i
5 l
4 f 1
1 2
1 9
t a
i i
i i
4 1
1 l
1 4
j o:\corresp\zcsteno 4-i-
i -- - _ _ . , , _ _, , _ , , . _ _ , , . , , ....,,,,v.
Jd--
L i
mag o ,,
)) / ,
r B xv _
~
f /,f , , -a _
A A > .. . e a n [ #
s J/ ) ,
.a _
s V 1
AgV A lIl\\ __ a j
e 9 g ilu,i Ea
-- y
4 g
_____g_lliliggg, s @111 ma _ ,,
x j ,
.a 3 ma _
a l l tl >
l 5 .
m_ s 3 4 U
, ma-i eg a
l wo i __ ,
t % waan yg1 . . .
l GA3a)IMAlpv s3u l
L
- _ . _ __= _ ~m m. ., .....m . . __ _ ._ . _ _ _ . . m . ._ _ ~ .. __
l l SRAIDWOOD UNIT 2 CYCLE 4 FUEL RELIABILITLY DATA l l Apen 1994 FRt Data Pustffcation Rete Constant N/A 1/see 1-131 = N/A Power = N/A % 5131/1-133 Ratio N/A 8-134 = N/A Letdown = N/A gens Fuel ReGelnMty index = N/A POWER I-131 1-132 1-133 1-134 l-135 Xe-133 0131/k133 LETDOWN LETDOWN RCS RCS CALC. REPORTED Rate DE1131 NORM DATE % RATIO LOW (GPM SP.VOL. T AVE SP.VOL. F_Rt FRt Cc9stant 0131 4/1/94 0:30 87.3 1.90E-02 8.92E-03 1.93E-02 4.54E-03 9.21E-03 9.84E-01 121.6 1.615E-02 576.5 2.23E-02 4.10E-02 4.10E-02 3.70E-05 2.53E-02 3.43E-02 4/1/94 4:00 85.8 2.07E-02 1.04E-02 2.00E-02 5.14E-03 9.82E-03 1.04E + 00 121.5 1.615E-02 576.6 2.23E-02 4.58F-02 4.58E-02 3.69E 05 2.73E-02 3.74E-02 4/1/94 7:30 83.4 1.94E-02 7.83E-03 1.63E-02 4.36E-03 8.30E-03 1.36E + 00 1.19E + 00 121.6 1.615E-02 575.5 2.23E-02 4.49E-02 4.49E-02 3.70E-05 2.48E-02 3.51E-02 4/1/94 11:30 81.5 1.90E-02 8.00E-03 1.69E-02 3.91E-03 7.59E-03 1.12E + 00 121.3 1.615E-02 575.5 2.23E-02 4.54E-02 4.54E-02 3.69E-05 2.45E-02 3.43E-02 4/1/94 15:30 79.4 2.33E-02 1.11E-02 2.10E-02 4.03E-03 8.55E-03 1.11 E + 00 121.5 1.615E-02 575.1 2.23E-02 5.80E-02 5.80E-02 3.69E-05 3.01E-02 4.21E-02 4/1/94 19:30 76.9 1.80E + 00 N/A 121.6 1.615E-02 574.6 2.23E-02 N/A N/A 3.70E-05 N/A 4/1/94 21:08 75.9 2.37E-02 1.06E-02 1.94E-02 3.91E-03 7.99E-03 1.22E + 00 121.5 1.615E-02 574.1 2.23E-02 6.32E-02 6.32E-02 3.69E-05 3.00E-02 4.28E-02 4/2/94 4:15 79.1 3.00E-02 1.30E-02 2.37E-02 4.54E-03 8 45E-03 1.30E + 00 121.7 1.615E-02 575.2 2.23E-02 7.73E-02 7.73E-02 3.70E-05 3 84E-02 5.57E-02 4/2/94 0-00 79.8 3.12E-02 1.21E-02 2.22E-02 4.10E-03 7.76E-03 1.31 E
- 00 141E+00 121.4 1.615E-02 575.5 2.23E-02 7.71E-02 7.71 E-02 3.69E-05 3.83E-02 5.63E-02 4/2/94 12:00 82.1 3.07E-02 1.23E-02 1.92E-02 4.19E-03 7.56E-03 1.60E + 00 121.5 1.615E-02 576.3 2.23E-02 7.28E-02 7.28E-02 3.69E-05 3.70E-02 5.54E-02 4/2/94 16:00 84.1 2.89E-02 1.12E-02 1.90E-02 4.32E-03 7.27E-03 1.52E +00 121.7 1.615E-02 576.5 2.23E-02 6.62E-02 6.62E-02 3.70E-05 3.51E-02 5.23E-02 4/2/94 20-05 85.6 2.74E-02 1.00E-02 1.70E-02 4.73E-03 6.93E-03 1.70E + 00 1.61E + 00 121.6 1.615E-02 575.9 2.23E-02 6.10E-02 6.10E-02 3.70E-05 3.30E-02 4.95E-02 4/3/94 0-30 87.5 2.44E-02 1.00E-02 1.59E-02 4.63E-03 6.99E-03 1.53E + 00 121.2 1.615E-02 576.0 2.23E-02 5.24E-02 5.24E-02 3.68E-05 2.97h-02 4.40E-02 4/3/94 4:05 88.4 2.34E-02 9.74E-03 1.58E-02 5.33E-03 7.33E-03 1.48E + 00 121.5 1.615E-02 576.1 2.23E-02 4.96E-02 4.96E-02 3.09E-05 2.87E-02 4.23E-02 4/3/94 8:00 88.7 2.09E-02 8.34E-03 1.39E-02 4.01E-03 6.83E-03 1.12E + 00 1.50E + 00 121.5 1.615E-02 576.5 2.23E-02 4.41 E-02 4.41 E-02 3.69E-05 2.56E-02 3.77E-02 4/3/94 12.0f' 90.5 1.96E-02 8.02E-03 1.33E-02 4.31E-03 7.60E-03 1.47E + 00 121.5 1.615E-02 577.1 2.23E-02 4.01E 02 4.01E-02 3.69E-05 2.42E-02 3.54E-02 4/3/04 16:00 92.6 1.93E-02 8.51E-03 1.43E-02 4.69E-03 7.88E-03 1.35E + 00 121.6 1.615E-02 577.2 2. 23E-02 3.81E-02 3.81E-02 3.70E-05 2.42E-02 3.49E-02 4/3/94 20:15 93.6 1.95E-02 8.50E-03 1.40E-02 5.17E-03 8. 28E-03 1.39E +00 121.6 1.615E 02 577.7 2. 23E-02 3.79E-02 3.79E-02 3.70E-05 2.43E-02 3.52E-02 4/4/94 0:55 96.3 1.89E-02 8.44E-03 1.38E-02 ti.30E-03 9.21E-03 1.37E + 00 121.4 1.615E-02 578.0 2.23E-02 3.51E-02 3.51E-02 3.69E-05 2.38E-02 3.41E-02 4/4/94 4:05 96 9 1.86E-02 7.94E-03 1.48E-02 5.09E-03 8.99E-03 1.26E + 00 121.5 1.615E-02 578.9 2.23E-02 3.452-02 3.43E-02 3.69E-05 2.37E-02 3.36E-02 4/4/94 ROO 9t,.5 1. 78E-02 7.63E-03 1.38E-02 4.78E-03 9.43E-03 1.63E + 00 1.29E + 00 121.5 1.615E-02 578.8 2.23E42 3 20E-02 3.20E-02 3.69E-05 2.26E-02 3.21E-02 4K/9412:00 99.6 1.80E-02 7.42E-03 1.56E-02 5.19E-03 9.37E-03 1.15E + 00 121.6 1.615E-02 579.6 2.23E-02 3.19E-02 3.19E-02 3.70E-05 2.33E-02 3.25E-02 4/4/94 19.50 99.7 1.66E-02 6.BSE-03 1.54E-02 5.53E-03 9.33E-03 1.86E + 00 1.00E + 00 121.3 1.615E-02 579.1 2.23E-02 2.92E-02 2.92E-02 3.69E-05 2.18E-02 2.99E-02 4/5/94 9:00 99.5 1.50E-02 6.40E-03 1.36E-02 5.08E-03 8.84E-03 1.48E + 00 1.10E +00 121.6 1.615E-02 579.4 2.23E-02 2.6eE-02 2.66E-02 3.70E-05 1.97E-02 2.71E-02 4/5/941k35 0.0 1.46E + 00 4.70E-01 1.60E + 00 7.45E-02 8.72E-01 2.22E + 00 9.13E-01 120.2 1.615E-02 558.7 2.23E-02 N/A N% 3.65E-05 1.98E + 00 2.61E + 00 4/5/94 22:00 0.0 1.23E + 00 1.94E 01 1.19E + 00 5.01E-01 1.03E + 00 120.9 1.615E-02 558.5 2.23E-02 N/A N/A 3.67E-05 1.80E + 00 2.21E + 00 4/6/94 0:40 0.0 9.76E-01 1.27E-01 8.96E-01 3.12E-01 1.09E + 00 1.615E-02 2.23E-02 N/A N/A N/A 1.25E + 00 N/A 4/'V94 4:15 0.0 6.93E-01 8.50E-02 5.49E-01 1.48E-01 1.26E + 00 1.615E-02 2.23E-02 N/A N/A N/A 8.55E-01 N/A Page 1
l
" ..L l
4/6/94 Fh00 0.0 4.64E-01 6.46E-02 3.30E-01 6.95E-02 1.51E + 00 1.41E + 00 1.615E-02 2.23E-02 N/A ~ N/A N/A 5.00E-01 N/A 4/6/94 12:00 0.0 3.08E-01 5.33E-02 1.94E-01 3.20E-02 1.59E +00 1.615E-02 2.23E-02 N/A N/A N/A 3.84E-01 N7A 4/6/94 16:10 0.0 2.03E-01 4.58E-02 1.18E-01 1.42E-02 1.72E +00 1.615E-02 2.23E-02 N/A N/A N/A 2.37E-01 N/A 416/94 20-15 0.0 1.46E-01 3.74E-02 6.95E-02 6 05E-03 1.87E + 00 2.10E + 00 1.615E-02 2.23E-02 N/A N/A N/A 1.86E-01 N/A 4/6/94 23:50 0.0 1.03E-01 3.25E-02 4.70E-02 2.99E-03 2.19E + 00 1.615E-02 2.23E-02 N/A N/A N/A 1.17E-01 N/A 4/7/94 3:50 0.0 6.86E-02 2.73E-02 2.92E-02 1.60E-03 2.36E + 00 1.615E-02 2.23E-02 N/A N/A N/A 7.75E-02 N/A R/7/94 200 0.O ' 6.03E-02 2.61E-02 2.22E-02 8.94E-04 1.23E + 00 2.72E +00 1.615E-02 2.23E-02 N/A N/A N/A 6.39E-02 N/A 4/7/94 ROO O.0 5.73E-02 2.42E-02 2.11E-02 7.36E-04 2.72E +00 ?.615E-02 2.23E-02 N/A N/A N/A 6.73E-02 N/A 4/7/94 12:00 0.0 5.47E-02 2.21E-02 1.65E-02 4.29E-04 3.32E + 00 1.6t SE-02 2.23E-02 N/A N/A N/A 5.99E-02 N/A 4/7/94 18:45 0.0 4.36E-02 2.05E-02 1.18E-02 1.36E + 00 3.76E + 00 1.615E-02 2.23E-02 N/A N/A N/A 4.74E 02 N/A 4/8/94 fA00 0.0 1.47E-02 1.30E-02 2.33E43 6.31E + 00 1.615E-02 2.23E-02 N/A N/A EA 1.78E-02 N/A
, 4/8/94 0-00 0.0 1.6eE-02 1.53E-02 2.54E-03 9.10E-01 6.54E + 00 1.615E-02 2.23E-02 NS N/A N/A 1.58E-02 N/A 1
Page 2
-- - - n. -- - - - - - - - - - __--.,-m----__ _ - - - - - - - - , - - - - _ - - - - , - - - - - - - _ _ - - _ . - a- a-- - - - - - - - - _ - - - . - - - - - - - , - - _ - - . _ - - _ _ - - - - - - - - - - . - _ - - - - - _ _ --.a -_a--w_---r _ - -- - - - . . - . . . . - - , - - . .
