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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)
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
7 Jb . < c LQ U *
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- Comraonwealth Edisoni bg 4 .; V .1400 Opus Pl;c] .
- p. g T, ,Jp Downers Grove, Illinois 605151
(, _~ ~ , - - -
y .
@.r~n _
- W e June 23, 1992 s
f, k * - -
t' se ,--
f ' , ,.
-f( Dt? Thomas l-::. Hurley, Director g . Office of Nuclear Reactor Regulation-P .U.S.'. Nuclear-Regulat7ty Commission y . Washington,~D.C. 20555
.-? Attnt' , Document Control Desk 6 '
Subject:
Braidwood Station Units I and 2'
^
Inservice Testing (IST). Programs for
- l. ' Pumpsfand-Valves
~ HE_DncheLJ1om 10-4MLani_50-151 y LReference (a). July 15, 1991, A.R. Checca letter
( s to Dr. T.E..Murley
( b' ) February 10,.1992, T. Simpkin letter 7
s to T.E. Murley 4
Dear;Dr.'Murley:
- ThefBr$1dwood Station (IST) Programs, fot Pumps and Valves (Revisions c5'and-Sa),are enclosed with.this.Intter and 1.1clude changes based on the
.tiomments presented in the teleconference held on June 12, 1992. This
- submitti.It replaces the reference _(a11 submittal in its entirety and
. . incorporates staff comments-for both the Byron and Braidwood programs.
' ~ ' Attachment'.A to.this letter presents a summary of the changes,.an
[ 4 J Attac'n- it B contains 1 the ' program.
'iae Revision 5/Sa.IST Program provides' supplemental information to that p
~
given:in Reference (b) for the following relief requests:
y
%; ReliefI ~ App C-
[ Hmb.e.t l LLn._ EckcLLpl.Lon
- VR-4 ~ ; 4- :A-paragraph was added-to incorporate the attempt made by
-Byron Station to acoustically test the 1/2CS008A&B check
~
.ph 34 -; valves using air. 1 7
I
~
VR-5 -- 5 This ' relief ' incorporates additional information regarding the method of test. The' acoustic " time-of-arrival"
~ '
' technique will be used to verify full stroke of the subject
, valves.
,s -
vn-17'- 7; 'This relief request-incorporates acoustic monitoring, in 1 addition =to~ monthly testing, to verify the opening capability of the 1/2SX101A solenoid valves.
'ZNLD/1896/1" h~' "]70@5 p pg, .OOy q u m m ,au. e a
.= _--
p.
Dr. Thomas E. Hurley' July 15,'.1991
.The-following list of relief requests require NRR review and approval _due to adding additional equipment and/or changes in the proposed alternate test method that was previouslyl approved, or the reller is being submitted for
' initial approval:
PR-02a . Exempt Pump Temperature Measurements PR-05' Use of Ultrasonic Flow Instrumentation VR-02 1/2CS020A/B Check Valves (previously submitted)
VR-04 1/2CS003A/B and 1/2CS008A/B Check Valves VR-05 1/2 SIB 948A-D and 1/2 SIB 956A-D Check Valves VR-08 1/2CC9518 1/2CC9534 Check Valves VR-09 1/2CV8113 Check Valves VR-10 1/2IA091 Check Valves VR-15 1/2RH8705A/B Check Valves VR-17 1/2SX101A Solenoid Valves VR-19 1/2AF001A Check Valves VR-20 Fixed Alert Ranges for Power Operated Valves VR-24 1/2PR032 Check Valves
'VR-25 1/2PS231A/B Check Valves VR-26 1/2RY804E and 1/2RYB047 Check Valves 1VR 1/2WOOO7A/B Check Valves
-In addition, the AFW SK Booster Fumps (1/2SXO4P) and their associated discharge check valves (1/2SX174) are being added, however, the testing of these components will not be fully implemented until the end 1992. This is
-due to the need to purchase new ultrasonic flow instrumentation to measure flow. Also, these pumps were added to PR-05 in order to ne the ultrasonic flow instrumentation to perform the Code testing.
Relief request, VR-20. requests approval for fixed alert ranges for all power operated valves and is currently approved for Byron Station. A Braidwood implementation schedule will be developed, once NRR approval is granted.
Please address any questions you'may have regarding this matter to this office.
Very truly yours, s . .
Q)T.H.
A Simpkin f
Nuclear Licensing Administrator cc: 'R.M. Pulsifer Resident Inspector-Braidwood B. Clayton-Region III ZFLD/1896/2
l ATTACH 4ENT A Summary of Changes-for. Revision 5/Sa i
of the-. Inservice Testing Program l Plan for Pumps and Valves ;
Draidwood Nuclear Station
' Section 3.0 --Inkle._oLCantents -
- - The: format of the Braidwood =. Inservice Testing (IST) program for pumps has been changed to coincide with the Byron Station program.
- 1. Added'a program-reference-section.
- 2. Changed ' note nwnbers to match Byron's.
m 3. .Added a technical approach and position section.
- 4. Changed relief request numbers to match Byron's.
- 5. PR-02a'is-being submitted to exempt bearing temperature measurements
-f rom all pumps' in the program.
Section 3.1 - EragranLDear.1_lELinn
- 1. Expanded this section-to incorporate Byron's additional information.
Section 3.2 -- Elsgr_e;n Re f erenner.t
~
l '. Added this'section to list vesious references used to develop the IST program, including NRC SERs.
Section 3.3 rump _ Tables d
t A. Eump Table Description
- 1. _Added an"T" character identifier to the " Code" fleid (for tracking purposes only).
-2. Added a statement to the " Test Interval" description concerning testing whental pump is not required to be operable.
.3.- Added a :" Remarks" field description, i :B. Eymp' Tables
_1. Added 'the . AB pumps to' the program for tracking purposes. only. Pump L Technical Approach and Position, PA-01 provides the explanation why these - punps will be . tracked by the IST program.
L 2. Deleted. the DO pumps f rom PE-03 because the permanently installed i flow instruments will be used.
- 3. ~ Changed PR-03 (Rev. 4).to PR-05 (Rev. 5) to match Byron's program.
-Rev. Sa added the SXO4P Sx Dooster pumps because-there are no q ; installed' flow meters for these pumps.
.4. ' Changed Note 2 to Note 3.
- 5. Changed Note 1 to Note 2.
-6. Added type of. driver to " pump name" column for the'AF pumps.
- 7. . Changed PR-04 to PR-06 to match Byron's program.
- 8. Changed PR-03'to'PR-05 to match Byron's program.
- 9. : Added " Pump" to the- WO pump description.
210. Added the 1/2SXO4P-SX Booster Pumps. The testing of these pumps will be implemented by the end.of 1992.
Page 1 (311/ZCTECH)
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Summary ~of Changes for. Revision 5/5a i4 ofLthe Inservice Tenting Program Plan for Pumps and Valvea Braidwood Nuclear Station Section 3.4 - Pump Notes
- 1. .This section was changed to reflect Byron's program numbering. Those notes which are not applicable to Braidwood's program are specifically identified.
. Note 5 - these pumps do not exist at Braidwood.
Note 6 - Rev. So added this note regarding the SX Dooster pwnp i implementation schedule.
Note 7 - Braidwood elected to track the AD pumps per the IST program versus a separate program.
' Section 3.5 - bgn2._.T_C.ChnLCALAPPL9AXhta AAd_PREiLLQnA
- 1. Added this section to implement standard IST program format and practices.
- 12. Added to describe how the AB pumps will be tested and tracked.
Section 3,6 - hune_RelleI_Faquefis
- 1. An approval status section/ step (9) was added to all relief requests to track both revision and approval for ease of review.
- 2. PR the total number of pumps was changed.
- 3. PR-02a - submitting this relief request to incorporate all pumps in the program. This is an-industry wide change (from measuring temperature yearly-to measuring vibration in velocity) and is acceptable to the NRC and ASME interested parties. Needs NRC approval. 4
- 4. PR changed to-PR-5 to match Dyron's program. Rev. Sa added the SX Booster. pumps, 1/2SXO4P. This relief was previously approved per the Rev. 4 SER.
- 5. PR changed to PR-6 to match Byron's. program.
- 6. - PR-7_- does not apply; these pumps do not exist at Braidwood.
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,n.. n n w.. . . , , -
Summary of Changes for-Revision 5/5a
-of the Inservice Testing Program
-Plan for Pumps and Valves Braldwood Nuclear Station
- Section 4.0'- Table _q1_ Contents i The format of the'Braidwood Inservice Testing (IST) program for valves has been changed to. coincide with the Byron Station program. 1
- 1. 'Added a program reference section.
- 2. Changed note numbers to match Byton's.
- 3. Added a technical approach and position section.
- 4. Changed relief request numbers to match Byron's, as close as practical.
Section 4.1. - EngrEn_Rescrintion
- 1. Expanded this section to incorporate Byron's additional information.
Specifically:
- a. Added status and requirements of the NRC approval on relief requests.
- b. Added paragraph describing scope of va've program.
- c. Added description of positions on stroke timing and check valve testing per Generic Letter 89-04.
- d. -Added required action range response when data falls outside acceptable limits. ,
- e. Added description of when new stroke time reference values are required.
Section 4.2 - EIngram Ref eLEDERS {
- 1. Added this section to list various references used in program development or that are pertinent to the program, including NRC SERs.
Section 4.3 - V_alyg_Tr.bles A. VALVA _ Table _D_egrIlgtion
- 1. Added a "T" character identifier to the " Code" field (for tracking purpcses only).
'2. Added field descriptions and columns for " Notes" and " Technical Approaches and Positions."
- 3. Added a " Remarks" field description.
- 4. Changed Ct description to CT/Bt to indicate the direction a check valve will be tested. Ct - for open direction and Bt - for closed direction.
- 5. Deleted the " maximum stroke time" and " system" fields. ,
D. y_alyg_Tnkles
- 1. Added the AB pump discharge check valves to the prograe for tracking purposes only. Valve Technical Approach and Position, VA-5 provides the explanation why these valves will be tracked by the IST program.
, 2. Added.new " Technical Approaches and Positions" and " Notes" columns.
- 3. Added VA-2 to all fail safe tested (Ft) valves.
- 4. Added VA-3 to all check valves and VA-1 to all power operated valves.
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Summary of Changes for Revision 5/La of the Inservice Testing Program
- Plan for Pumps and Valves Braidwood Nuclear Station B. V_clye__T <i (continued)
- 5. 1/2AF001A/B - added Bt at RR per VR-19,
- 6. 1/2Ar014A-H - added Bt at CS and Notes 12 and 30, 7 1/2CC9437A - deleted passive from remar ks and added an TT test.
- 8. 1/2CC9463A/B - added Ct/Bt at CS, XL at OP and Note 32.
- 9. OCC9464 - added Ct/Dt at CS, Xt at OP and Note 32.
- 10. 1/20C9486 - added Bt at RR per VR-8 and changed Ct to GP per Rev. Sa.
- 11. 1/2CC9518 - added Bt at RR per VR-8 and Note 24, deleted passive from remarks.
- 12. 1/2CC9534 - added Bt at RR per VR-B and Note 24, deleted passive from remarks.
- 13. 1/2CS008A/B - added Bt at RR per VR-4.
- 14. 1/2CV112B/C - added Note 28.
- 15. 1/2CV8113 - added Ct/Bt at RR per VR-9 and Note 24, deleted passive from remarks. 1/2CV8100 and 1/2CVB112 frequency changed to RR.
- 16. 1/2CV8442 - added Note 29.
- 17. 1/2CVB480A/B - added Bt at OP and Note 31.
- 18. 1/2CV8481A/B - added Bt at RR per VF-15.
- 19. 1/ 2 CV 854 6 - changed Ct at CS to Ct at RR per VR-lb and added Note 26,
- 20. 1/2D0003A-C - added Bt at OP.
- 21. 1/2FP010 - corrected valve type to globe (GL).
- 22. 1/2FWO34A-D - renumbered Note 18 to 21.
- 23. 1/21A091 - added Bt at RR per VR-10, deleted passive from remarks.
- 24. 1/2MS101A-D - changed valve type (GA to GL).
- 25. 1/2PR002G/H - added passive to remarks, deleted VP-23.
- 26. 1/2PR032 - added Bt at RR per VR-24, deleted passive from remarks.
- 27. 1/2PS228A/B - changed from globe to gate type valves.
- 28. 1/2PS229A/B - changed from globe to gate type valves.
- 29. 1/2PS230A/B - changed from 1" globe to 0.5" gate type valves per Mod M20-1-88-060. ~
- 30. 1/2PS231A/B - added Bt at RR per VR-25; changed Note 21 to Note 22 -
and category form C to AC.
- 31. 1/2RE1003 - deleted VR-12,
- 32. 1/2RE9157 - deleted VR-12.
- 33. 1/ 2RE9159A/B - deleted VR-12.
- 34. 1/2RE9160A/B - deleted VR-12.
- 35. 1/2RHB705A/B - added CL/Bt at RR per RV-15 and Notes 24 and 35,
- 36. 1/2RHB730A/B - added Bt at CS per Note 8.
- 37. 1/2RYO75 - Passive valve added due to Type C tested per App. J.
- 38. 1/2RY455A - changed St at OP to St at CS per Note 36.
- 39. 1/2RY456 - changed St at GP to St at CS per Note 36.
- 40. 1/2RY8025 - deleted passive from remarks.
- 41. 1/2RY8046 - added Bt at RR per VR-26, deleted passive from remarks.
- 42. 1/2RY8047 - added Bt at RR per VR-26, deleted passive from remarks.
- 43. 1/2SA032/33 - changed valve type (GA to GL).
- 44. 1/2SD002A-H - deleted VR-1 and added Note 34
- 45. 1/2SD005A-D - deleted VR-1 and added Note 34.
- 46. 1/2 SIB 815 - added Bt at RR per VR-15; changed Ct at CS to Ct at PR per VR-15.
- 47. 1/2 SIB 818A-D - added Bt at RE per VR-15 and Note 23.
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1 l
Summary of Changes for Revision-5/5a of-the Inservice Testing Program Plan for Pumps and Valves Braidwood Nu-lear Station D. . Valve Tahics. (continued)
- 48. .1/2SI8819A-D - added DL at RR pet VR-15 and Note 23.
4 9. - 1/2SI8841A/B - added Bt at RR per VR-15; changed Ct at CS to Ct at RH per VR-15. +
- 50. 1/2 SIB 871, 1/2518871 and 1/2S18888 - deleted passive from remarks.
- 51. 1/2 SIB 900A-B - added Bt at RR per VR-15; " hanged Ct at CS to CL at RR per VR-15.
- 52. 1/2SI8905A-D - added Bt at RR per VR-lb.
53, 1/2518919A/B - added Bt at OP and Note 31.
L4. 1/2 SIB 922A/B - added Dt at RR per VR-3.
- 55. 1/2S18926 - added Note 25.
56, 1/2SI8948A/B - added Bt at RR per VR-5; i 5 ed Ct at CS per VR-5:
added Note 23 to the 1/2SI8948A/B valves.
-57. 1/2SI8949A-D _added Bt at RR per VR-15.
- 58. 1/2SI8956A/B -Ladded'Bt at RR per VR-5; deleted Ct at CS-per VR-5.
- 59. 1/2SI8958A/B --added Note 27.
- 60. 1/2SIE964 - deleted passive from remarks.
- 61. 1/2518968 - added passive to remarks; deleted VR-18 per Rev. Sa.
- 62. 1/2SX002A/B - added Bt at OP.
- 63. 1/2SX016A/B - deleted passive from remarks.
- 64. -1/2SX027A/B - deleted passive from remarks.
- 65. 1/2SX147A/B - added control valves to program per Byron's latest submittal' .
- 66. 1/2SX174 - added these check valves per Rev. Sa.
67, 1/2VQ001A/B - deleted passive Iron remarks.
- 68. 1/2VQ002A/B - deleted passive from remarks.
- 69. 1/2VQ003 - deleted passive from remarks.
~
- 70. 1/2VQ004A/B - deleted passive from remarks.
- 71. 1/2VQ005A/B/C - deleted passive from remarks.
- 72. 1/2WOOO7A/B.- added Bt at RR per VR-27, deleted passive from remarks.
Section 4.4 - Valve Notes
- 1. This section was changed to reflect Byron's program numbering. Those notes which are not applicable to Braidwood's progrmn are specifically identified.
- 2. Sentence added to Note 6 regarding GL 89-04.
- 3. Changed. Note 18 to 21.
- 5. _ Changed. Note 21 to 22.
- 6. Added Notes 23 through 36.
l Section 4.5 - Y_al.ve Inchniral_AppInechts_nnd_P.ositions
- 1. ' Added this section to implement standard IST program format and
-practices.
- 2. Added VA-1 through 4 to coincide with Dyron's program. Also, VR-04 limiting values of full stroke were changed to coincide with those approved by NRR for Byron Station.
- 3. Added VA-5 to describe how the AB pump discharge check valves will be tested and tracked.
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Summary of Changes for Revision 5/Sa of the Inservice Testing Program Plan for Pumps and Valses Ut aidwood Nuclear St ation Section 4.6 - hl_ye_RelieLEequests
- 1. An approval status section/ step (9) was added to all relief requests to track both tevision and approval for ease of review.
- 2. VR Revised to document GL 89-04, Attachmant 1, Item 10 concerning trending of CIVs sir,ed six inches or greater. ASME Section XI IWV-3427(a) will not be utilized. Also, valves 3/2SD002A-H and 1/2SD005A-D were removed per Technical Spec i ficat ion Amendment 826.
This relief request is in accordance with GL RQ-04 requirements, and is pre-approved. Added 1/2RYO75 due to Appandix J, Type C tested.
- 3. VR Provided additional information for the disassenbly and inspection sample plan lie n GL 89-04. This revision incorporates the latest Byron discussions with NRR. This relief request is in accordance with GL 89-04 requirements, and is pre-approved. Rev. Sa added mixed hazardous waste considerations and was submitted as a separate response for the Rev. 4 SER.
- 4. VR Added back flow test code (Bt' to section 4.
- 5. Vk Provided additional information for the disassenhly and inspection sample plan per GL 89-04. This revision incorpotates the latest Byron discussions with NRR. This relief request is in accordance with GL 89 0% requirements, and is pr<-approved. Added acoustic test results from Byron for the 1/2CS008A/B check valves per Rev. Sa.
- 6. VR Added additional information regarding acoustic testing of these valves and provided justification for performing the Ct test during refueling only. The refueling frequency needs NRC review and approval.
- 7. VR-8 Added valves 1/2CC9518 and 1/2CC9534 with supporting information. These additions need NRC review and approval. Rev. Sa added additional technical information and justification.
- 8. VR Added valves 1/2CV8113 with supporting iniormation. These additions need NRC review and approval. Rov. Sa added additional ~
technical information and justification.
- 9. VR Added valves 1/2IA091 with supporting information. These additions need NRC review and approval. Rev. La added additional technical information and justifiuntion.
- 10. VR Removed the RE system valves from this relief per system engineers request. NRC approval is not required.
- 11. VR Added valves 1/2RH8705A, B and 1/2518818A-D vith supporting justification. In addition, the Ct testing of all these valves is requested to be done on a refueling basis only; additional justification has been provided. These additions need NRC review and approval. Rev. Sa added additional technical information and justification.
- 12. VR Additional information and justification was added to incorporate Byton's SER items. Rev. Se incorporates acoustic monitoring for these solenoid velves as an additional means to monitor for degradetion.
- 13. VR deleted per Rev Sa.
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. . . . ~ . . . _ . .. . . - . _ , ~ . . .-. .- . - - _ _ .
Summary of Changes for Revision 5/Sa l of the' Inservice Testing Progrwn Plan .for: Pumps and Valves
~
-Braidwood Nuclear Station-Section 4.6 - Ealve Psallef Requests (continued)
- 14. - VR-19~- This is a new relie5 tequeEt for the 1/2AF001A, D valves.
This relief incorpor ates the lastest Byron /NRR approval Rev. Sa incorporates acoustic monitoring versus-disassembly and-inspection.
- 15. ' VR added to request fixed alert ranges for power operated per Rev. Sa.
- 16. VR deleted per Rev. Sa. l
- 17. VR Rev. Sa added additional technical information and justification.
11 8 . VR Rev. Sa added additional technical information and justification.
- 19. VR Rev. Sa.added additional technical information and
. justification.
20 VR Rev. Sa added additional technical information and
- justification.
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