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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
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DEC - 31992 Docket No. 50-456 Docket No. 50-457 Commonwealth Edison Company ATTN: Mr. Cordell Reed Senior Vice President Licensing Department - Suite 300 Opus West III 1400 Opus Place Downers Grove, IL 60515
Dear Mr. Reed:
SUBJECT:
REQUALIFICATION PROGRAM EVALUATION Arrangements have been made between Mr. Neal Sanborn, Training Supervisor and T. Reidinger, Chief Examiner for an evaluation of the requalification program and licensed personnel at your Braidwood facility. The evaluation visit is scheduled for the week of April 19, 1993. The requalification examinations and the subsequent evaluation of the facility requalification program will be performed in accordance with sections 601 through 604 of NUREG 1021, Operator Licensing Examiner Standards, Revision 6.
You are encouraged to ensure that your training staff and proposed examinees are familiar with these standards.
For the examiners to adequately prepare for this visit, it will be necessary for the facility to furnish the approved items listed in Enclosure 1, " Reference Material Requirements."
Failure to supply the reference material as required by Enclosure 1 may result in postponement of the examination.- We have offered Mr. Sanborn the opportunity to provide a proposed requalification examination. Submittal of proposed examinations is optional-and in addition to the material requirements of Enclosure 1. If you decide to submit a proposed examination, we request that we receive the proposed simulator-scenarios at least 45 days in advance of the examination week. We also request that you provide a copy of the scenarios to U.S. Nuclear Regulatory Commission, ATTN: Chief, LOLB,-Washington, D.C. 20555. Those personnel involved in the development of the-proposed examination will become subject to the security restrictions described below.
Mr.Sanborn has been advised of our reference material requirements, propused examination option, and where these items are to be sent, You are requested to designate at least one employee to be a member of a joint NRC-facility examination team. The employee shall be an active SRO (per the requirements of 10 CFR 55.53(e) or-(f)) from the Braidwood Operations Department. You are encouraged to designate a second employee from the training staff f
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DEC 3 G32 CommonwealthI. Edison Company 2 l
- 7 to be a member of-the examination team. -This employee should be-an active _SRO par the requirements of 10 CFR 55.53(e) or (f)),
but may be' a_ facility or INPO certified; instructor.E If. desired and agreed to by the Chief Examiner, you may designate one additional employee from the examination team.: -In addition to ;
these individuals,-a simulator operator ~must be madefavailable for scenario preview and validation during the onsite examination preparation week. In some cases, it may be necessary to designate a simulator operator during the test item review; period. This individual will also be subject to the examination security agreement.
^
Any facility representatives under the security c'eeement shall be restricted from knowingly communicating by an, means the.
content or scope of the examination to unauthorized persons and-from participating in any facility programs such as instruction, -
examination, or tutoring in which an identified'requalification examinee (s) will be present. These restrictions shall apply from the day that the fccility representative understands that he or
- she has specialized knowledge of the. examination. - The Chief:
Examiner will determine when: facility representatives have '
4 received specialized knowledge concerning the examination and require execution of an examination security agreement. In most.
cases, the examination team members will not be required to enter into an examination security agreement more than 60 days prior'to the examination week. The simulator operator _will normally become subject to the requirements during'the examination-preparation and validation week but,_in some cases, this may occur as much as130 days prior to the examination week-to support operating test item review and revision.
The facility shall identify to the Nhc 60 days prior to_the ,
examination administration date, the proposed operators, including crew composition, for the examination. This .
information shouldzbe provided by the fadility-training staffLto the NRC's Chief Examiner.
The facility management'is responsible for providing adequate space and accommodations to. properly develop and: conduct the; examinations. Enclosure 2, " Administration of.Requalification?
Examinations," describes our requirements for developing and-
_ conductingfthe examinations. Mr. Sanborn has also been informed
- of
- these-requirements. _Also,-.a: facility operations-management representative-(as a minimum, first11evel above shift supervisor) should-observe the simulation facility examination process at the-site.
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DEC - 3 52 Commonwealth Edison Company 3 Enclosure 3 contains the "NRC Rules and Guidance for Examinees"
'that will be in effect during the administration of the written examination. The facility management is responsible for ensuring that all operators are aware of these rules.
Please review the guidance promulgated in Revision 6 to NUREG-1021 pertaining to the content and scope of simulator examination scenarios. The scenario examination bank should
, cover the entire spectrum of Emergency Operating Procedures (EOPO , including alternate decision paths within EOPs, and should incorporate a range of failures with varying degrees of severity for the same type of event. Each scenario should contain sirultaneous events that require that the crew prioritize actions and assign crew members to particular tasks. Each scenario should also require that the crew determine when to transition between EOPs and determine which actions to take within the EOPs.
This request is covered by Office of Management and Budget (OMB)
Clearance Number 3150-0101 which expires May 31, 1995. This estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, copying and mailing the required material. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Information and Records Management Branch, MNBB-7714, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0101), Office of Information and Regulatory Affairs, NEOB-3019, Office of Management and Budget, Washington, D.C. 20503.
Thank you for your consideration in this matter. If you have any questions on the evaluation process, please contact T. Reidinger at (708)/790-5551.
Sincerely, Ob 9 % L S G G 7( *8?fi3 C. MISHT Geoffrey C. Wright, Chief Operations Branch
Enclosures:
- 1. Refetence Material Requirements
- 2. Administration of Requalification Examinations
- 3. NRC Rules and Guidance for Examinees See Attached Distribution RIII RII .
l RII)t 8 ,RIIIo hD12/p (s%f
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Re ger/cg g ur ick W yis 12/$ /92 T 12/,1/92 12/j(/92 /92
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Commonwealth Edison Company 4 EC - 3 G31 Distribution cc w/ enclosures:
M. Wallace, Vice President, FWR Operations T. Kovach, Nuclear ;
Licensing Manager T. Simpkins, Nuclear Licensing Administrator K. Kofron, Station Manager A. Haeger, Regulatory Assurance Supervisor DCD/DCB (RIDS)
OC/LFDCB Resident Inspectors, Byron, Braidwood, Zion D. W. Cassel, Jr., Esq.
Richard Hubbard J. W. McCaffrey, Chief, Public Utilities Division R. M. Pulsifer, LPM, NRR Robert Newmann, Office of Public Counsel, State of Illinois Center State Liaison Officer A. R. Checca, Training Manager cc w/o enclosures:
R. M. Gallo, Branch Chief, OLB R. M. Pulsifer, Project Manager, NRR M. J. Farber, Section Chief, DRP y
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EECLOSURE 1 REFERENCE MATIlGAL REOUIREMZNTS Test items to support all aspects of the roqualification ;
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examinatic.1 must be provided to the NRC 60 days prior to the examination dato.
All test items should be developed in accordance with the .'
guidolinos provided in sections 602 through 604 of NUREG 1021, operator Licensing Examinor Standards, and their respectivo attachments.
For.the first roqualification ovaluation at the facility, the submittal must contain at leasts
- 700 test items for uso in tho writton examination. They should be equally divided betwoon the two sections of the examination and there must be at least 350 test items for use in each section.
- 75 job performanco measures (SPMs) for use on the walk-through portion of the operating examination. To the extent possible, approximately 40% of the JPMs should evaluato "in plant" tasks (systu1/ component operation outside the control room).
- 15 Jimulator scenarios of approximately 50-minutos each in length for uso on the simulator portion of the operating examination for examinations administered in one week.
For subsequent roqualification examjnations facilition are expected to make submittals reflecting progress toward the following targets over the next 5 years t-tter the initial evaluation visit i e A m'inimum of 700 test items for uso in the written examination cqually divided betwoon the two sections of the written examination and which cover all safety related olomonts of the facility joD task analysis (JTA). The bank shall be dynamic in nature, in that at least 150 questions a year shall be reviewed, revised or generated. New questions that are developed should cover equipment and system modification, recent industry and licensoo events and procedural changes.
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JPMs to evaluate each operator and senior operator safety related task identified in the facility JTA, which meet the criteria in ES-603. The JPM bank should expand at a rate of ut least 10 JPMs per year until this goal is reached. It is estimated that 125-150 JPMs will be the final result.
Development of the questions associated with the JPMs shall also continue, such that there is a representative sample of questions given the knowledges associated with the task listed in the JTA.
- A bank of at Icast 30 simulator scenarios which reflect all p),usible or expected abnormal and emergency situations to which control room operators are expected to respond or control. At least 5 scenarios por year should be generated until all aspects of the emergency operating procedures are covered with sufficient variation in the type and scope of ,
initiating events and level of degradation.
For all roqualification examination and evaluation visito, the facility,shall:
- submit an Examination Test Outline / Sample Plan which meets tne requirements of Eh-601, Attachment 2;
- provide the associated examination banks (written, simulator and JPM) and associated reference material. At a minimum -
this shall include Technical Specifications, abnormal and emergency operating procedures, and emergency plan procedures utilized in the requalification training;
- provide additional reference material cs requested by the Chief Examiner.
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ENCLOSURE 2 ADMINISTRATION OP REQUALIFICATIQN EXAMINATIONS 2
l 1. An evaluation of at least twelve facility licensed operators j is required for o program evaluation. Normally the crew f
scheduled for requalification training during the period selected for the program evaluation should be selected. The sample will include other licensed operators who are not routinely performing shift duties or are not maintaining an active license por 10 CFR 55.53(c). The restrictions on crew composition in the simulator are described in ES-601(C.1.b.) and ES-604.
- 2. The simulator and simulator operator (s) shall be provided l for examination development. The date(s) and duration of )
time needed to develop the examinations will be agreed upon I by the chief examiner and the facility.
- 3. The reference material used in the simulator vill be reviewed by the chief examiner. No material will be used i thp. is colely used for training.
- 4. A single room shall be provided for completing Section B of I
the written examination. The location of this room and supporting rest room facilities shall be such as to prevent-contact with all other facility and/or contractor personnel i for the duration of the examination. !
- 5. Minimum spacing is required to ensure examination integrity and will 1x3 ovaluated by the chief examiner._ Minimum ,
spacing consists of one examinee per table and a 3-foot space between tables. No wall charts, models, and/or other training materials shall be present in the examination room.
- 6. Copics of reference material for Section B of the written examination shall be provided for each examinee. The reference material will be reviewed by the chief examiner '
and will consist of Technical Specifications, operating / abnormal procedures, administrative procedures, and Emergency Plans as availabic to the plant. operators.
- 7. The NRC no longnr requires the facility licensee to videotape dynamic simulator examinations. If the facility licensee requests to videotape the examination, any use of the tape must be completed before the NRC leaves the site at the end of the examination. If a disagreement over the grading of a licensee still exists at the end-of the-
, examination week, the facility licensee may retain the tape b for the sole purpose of submitting it to support _a request A for regrade by the NRC. During the regrade, the NRC will [
review only the-portion of-the videotape under contention.
ENCLOSURE 2 (Cont'd) I
- 8. An attempt will be made to distinguish between RO and SHO '
knowledge and abilities to the extent that such a distinction is supported by the facility training matarlais. !
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- 9. Prudent scheduling of exam week activities is (ntartant to help alleviato undue stress on the operators- four training staff and the Chief Examiner should work very closely in formulating a schedule which does not result in excessive ,
delays in crews or individuals being administered their examination. The following are some suggestions for structuring the exam activities to achieve this purpose:
- Don't bring in crews or individuals well before their scheduled exam times.
- When examining operators in groups, it is better to hold the group just completing their exam vice the group that are taking their exam Inter.
- Following simuldtor scenarios, the facility evaluators and NRC examiners should quickly determine whether follow-up questioning is required, so tha* the crew may be released to talk among themselves about the scenario.
- Ensure that time validation of JPMs, particularly_those performed in the simulator, is conducted accurately. A reasonable schedule should be established to prevent operators from waiting for simulator availability to complete their JPMs.
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f ENCLOSURE 3 !
t NRC RULES AND GUIDANCE FOR EXAMINEES ,
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- 1. Use black ink or dark pencil ONLY to facilitate legib'.e reproductions.
- 2. Print your name in the blank provided on the cover sheet of ,
the examination. '
- 3. Fill in the date on the cover sheet of the examination, if necessary.
- 4. Answer each question on the examination. If_ additional paper is required, use only the lined paper provided by the examiner.
- 5. Use abbreviations only if they are common 7qy used in facility ,
literature.
- 6. The point value for each question is indicated in >
parentheses after the question and can be used as a guide for the depth of answer required.
- 7. Show all calculations, methods, or assumptions used to obtain an answer to a mathematical problem whether asked for.
i_ in the question or not. ,
- 8. Unless solicited, the location of references need not be stated.
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- 9. Proportional grading will be applied. Any additional-wrong '
information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give
. five responses, each response will be worth-0.20 points. If one of your five_ responses is incorrect, 0.20-will be.
deducted and your. total credit for that question will- be l
0.80, even though you may have listed the four correct i responses in the answer key.=
- 10. Partial credit may be given.- Therefore, ANSWER ALL PARTS OF THE QUESTION-AND DO NOT LEAVE ANY ANSWERS; BLANK. Partial credit will NOT be_given on multiple choice' questions.
- 11. If parts of the_ examination are not. clear with respect to
. their intent, ask questions of the examiner only.
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ENCLOSURE 3 (Cont'd)
- 12. You must sign the statement on the cover sheet that
,dicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTER the examination has been completed.
- 33. Rest room trips are to be limited and only one examince at a time may leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromise.
- 14. Cheating on +he examination would result in a revocation of your licen<a a cc 14 result in more severe penalties.
- 15. Each sectit' el Cie d"; .ation is designed to take a approximatch 91 , "atst $o complete.
- lou will be given two hours to comp 1cta .;ach section to allow for thirty minutes of review.
- 16. The examination h.2s been time validated by knoaledgeable persons. You should be aware that not every answer needs to be verified by consulting a reference, and excessive usage of reference material may cause you to not complete the examination in the allotted time.
- 17. Due to the existence of questionr that will require all examinees to refer to the same indications or controls, particular care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating. -
- 18. When you are finished and have turned in your completed examination, leave the examination area.
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