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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:OUTGOING CORRESPONDENCE
MONTHYEARML20217G9791999-10-14014 October 1999
Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2
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
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
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
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
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
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
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
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
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
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)
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
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
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
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
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
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
ML20207A5891999-05-20020 May 1999
Forwards Insp Repts 50-456/99-05 & 50-457/99-05 on 990405-23.Two non-cited Violations Identified
ML20206U4641999-05-18018 May 1999
Responds to Util 990517 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3.0.3. Documents 990516 Telcon with Licensee Re NOED
ML20206N4791999-05-13013 May 1999
Forwards RAI Re 980529 Amend Request for Byron & Braidwood to Credit Automatic PORV Operation for Mitigation of Inadvertent SI at Power Accident.Response Requested 60 Days After Receipt Date
ML20206Q5321999-05-11011 May 1999
Forwards Insp Repts 50-456/99-06 & 50-457/99-06 on 990302-0413.Configuration Control Error Resulted in Isolation of Unit 1 Emergency Boration Flow Path Through Designated Boric Acid Pump for Period of 3 H Occurred
ML20206H8161999-05-0505 May 1999
Confirms Discussion Re Meeting to Be Conducted on 990527 at Braidwood Station Training Building.Meeting Will Discuss Braidwood Station Performance as Described in Most Recent Plant Performance Review
ML20206E7021999-05-0303 May 1999
Advises That Info Contained in Document Entitled, Licensing Rept for Sf Rack Installation at Byron & Braidwood Stations, HI-982083,will Be Withheld from Public Disclosure Per 10CFR2.790
ML20205G9631999-03-26026 March 1999
Advises of Planned Insp Effort Resulting from Braidwood Plant Performance Review for Period 870830-990131.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 6 Months Encl
ML20204J4241999-03-23023 March 1999
Forwards Insp Repts 50-456/99-04 & 50-457/99-04 on 990222-24 & 0303 Onsite & 0309 & 11 Region 3 Ofc.No Violations Noted. Implementation of Physical Security Plan Was Examined
ML20204J9001999-03-23023 March 1999
Forwards Insp Repts 50-456/99-02 & 50-457/99-02 on 990120- 0301.No Violations Noted
ML20204G2031999-03-22022 March 1999
Forwards Year 2000 Readiness Audit Rept Which Documents Results of NRR Audit Conducted at Facility from 990124-28
ML20204C7201999-03-16016 March 1999
Ack Receipt of Expressing Concern Over Sale of Certain Properties by Commonwealth Edison Co
ML20204E3341999-03-16016 March 1999
Expresses Appreciation for Re Concerns Over Sale of Certain Properties by Licensee.No Regulatory Basis for NRC to Require Util to Rely on strip-mine Ponds as Suppl Source of Cooling Water
ML20204E2801999-03-16016 March 1999
Ack Receipt of Rev 3M to Portions of Braidwood Nuclear Power Generating Station Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Ceco Determinations That Changes in Rev 3M Do Not Decrease Effectiveness of Plan
ML20207J9741999-03-11011 March 1999
Discusses Rev 3,to Portions of Braidwood Power Station EP Site Annex.Based on Licensee Determinations That Changes Do Not Decrease Effectiveness of EP & Plan Continues to Meet Standards of 10CFR50.47(b),NRC Approval Not Required
ML20203E9521999-02-11011 February 1999
Forwards Insp Rept 50-456/98-16 on 980916-990121.No Violations Were Identified.Insp Was Exam of Activities Re Engineering & Maint Activities for Replacement of Steam Generators for Compliance with Commission Regulations
ML20203F2541999-02-10010 February 1999
Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function
ML20203C9761999-02-0808 February 1999
Ack Receipt of ,Which Transmitted Changes Identified as Rev 44 to Security Plan.No NRC Approval Required
ML20203A4601999-02-0505 February 1999
Ack Receipt of 981109 Evaluation of Indication in Base Metal of Braidwood Station,Unit 1,main Steam Piping Sys Elbow
ML20203A3641999-02-0303 February 1999
Forwards Copy of FEMA Evaluation Rept for 980520 Emergency Preparedness Exercise at Braidwood.One Deficiency & Three Areas Requiring Corrective Action Identified.Deficiency Corrected During Remedial Exercise Held on 980806
ML20199E6561999-01-15015 January 1999
Discusses Unresolved Security Item Re Adequacy of Compensatory Measures Implemented for Section of Vehicle Barrier Sys.Issue Briefly Described as Listed
ML20199E1351999-01-0808 January 1999
Forwards Revised Dates for Engineering & Technical Support Insp,Emergency Planning Insp,Security Insp & Operational Assessment Insp for Braidwood
IR 05000456/19980141999-01-0505 January 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts on 50-456/98-14 & 50-457/98-14 Issued on 981117
ML20198R0741998-12-30030 December 1998
Forwards Insp Repts 50-456/98-20 & 50-457/98-20 on 981020-1207.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls
ML20197J6831998-12-10010 December 1998
Forwards Insp Repts 50-456/98-21 & 50-457/98-21 on 981110- 24.No Violations Noted.Insp Reviewed Corrective Actions for Previously Identified Issues
ML20197H4261998-12-0404 December 1998
Forwards Insp Rept 50-456/98-18 on 981015-23 & 1109-10.No Violations Noted.Some Weaknesses Identified in Operator Performance & Training
ML20197K1311998-12-0202 December 1998
Forwards Planned Insp Effort for Next 6 Months at Plant.Info Provided to Minimize Resource Impact on Staff & Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite
1999-09-06
[Table view] |
See also: IR 05000456/1997010
Text
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l June 26, 1997
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Mr. H. G. Stanley
l Site Vice President
Braidwood Nuclear Power Station
Commonwealth Edison Company
R.R. #1, Box 84
Braceville, IL 60407
SUBJECT: NRC INSPECTION REPORT 50-456/97010(DRS)
Dear Mr. Stanley: ;
On June 2,1997, the NRC completed an inspection at your Braidwood, Unit 1, reactor
facility. The enclosed report presents the results of that inspection.
The inspection included a review of inservice inspection activities and the examination of
steam generator tubes. Your efforts to evaluate tube integrity by assessing growth rates
for outside diameter stress corrosion cracking using historical eddy current data
reviews / comparisons and in situ pressure testing were indicative of an aggressive program.
The decision to provide additional oversight of the contractors' activities and procedures
$ for eddy current examination of the steam generator tubing was considered a program
improvement.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter
and the enclosed inspection report will be placed in the NRC Public Document Room.
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
/s/ John ti. Jacobson (for)
John A. Grobe, Acting Director f
Division of Reactor Safety g
Docket No. 50-456 A I
Enclosure: Inspection Report 50-456/97010(DRS)
See Attached Distribution
llllllllNllllllElllRI,Illlllll
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DOCUMENT NAME: G:\DRS\ BRA 97010.DRS (See Previous Concurrence)
To rocsive a copy of this document, indicate in the box 'C" = Copy w/o attach /enci T = Copy w/ attach /enci "N" = Nopopy
OFFICE Rill:DRS l Rlll:DRS l Rill:DRP l Rill:DRh _ J
NAME Schapker/kjc Gavuta Lanksbury JacopilQf)Iftd, cf
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DATE 06/ /97 06/ /97 06/ /97 06/f$
OFFICIAL RECORD COPY
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PDR ADOCK 05000456
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.
Mr. H. G. Stanley
Site Vice President
Braidwood Nuclear Power Station
Commonwealth Edison Company
R.R. #1, Box 84
Braceville, IL 60407
SUBJECT: NRC INSPECTION REPORT 50-456/97010(DRS)
Dear Mr. Stanley:
On June 2,1997, the NRC completed an inspection at your Braidwood, Unit 1, reactor
facility. The enclosed report presents the results of that inspection.
The inspection included a review of inservice inspection activities and the examination of
steam generator tubes. Your efforts to evaluate tube integrity by assessing growth rates
for outside diameter stress corrosion cracking using historical eddy current data
'
reviews / comparisons P.nd in situ pressure testing were indicative of an aggressive program.
The decision to previde additional oversight of the contractors' activities and procedures
for eddy current examination of the steam generator tubing was considered a program
improvement.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter
and the enclosed inspection report will be placed in the NRC Public Document Room.
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
John A. Grobe, Acting Director
Division of Reactor Safety
Docket No. 50-456
Enclosure: Inspection Report 50-456/97010(DRS)
See Attached Distribution
DOCUMENT NAME: G:\DRS\ BRA 97010.DRS
'
To receive a copy of this document, indicate in the box 'C" = Copy, w/o attach!enct 'E" = Copy w/ attach /enct "N" = No copy
OFFICE Rlll:DRS ]g Rlli:DRS ,j N Rill:DRP [ Rlli:DRS l
NAME Schapker/kjcJ/L -Gavula y fg LanksburyQ% Jacobson/Grobe
DATE 06//9/97 f/ 06/ g /9{ j" 06/u /97 06/ /97
V OFFICIAL RECORD COPY
. .. . - . - - . _ _ - . . -
,
.
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- H. G. Stanley - 2
June 26, 1997
1
cc w/ encl: T. J. Maiman, Senior Vice President,
i Nuclear Operations Division
'. D. A. Sager, Vice President,
! Generation Support
H. W. Keiser, Chief Nuclear
i Operating Officer
-
T. Tulon, Station Manager
j T. Simpken, Regulatory Assurance
'
Supervisor
i 1. Johnson, Acting Nuclear
-
Regulatory Services Manager
i Document Control Desk - Licensing
l Richard Hubbard
i Nathan Schloss, Economist,
l Office of the Attorney General
4 State Liaison Officer
- Chairman, Illinois Commerce Commission
l Distribution:
'
Docket File w/enct Rlli PRR w/ encl J. L. Caldwell, Rlll w/enci
PUBLIC IE-01 w/enct SRIs, Braidwood, Byron, Rlli Enf. Coordinator w/enci
, OC/LFDCB w/enci Zion w/ encl R. A. Capra, NRR w/enci
4
DRP w/enct LPM, NRR w/ encl TSS w/enci
DRS w/enci A. B. Beach, Rlll w/ encl CAA1 w/enci
4
