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Category:EXAMINATION REPORT
MONTHYEARIR 05000286/19870031987-04-12012 April 1987 Exam Rept 50-286/87-03OL on 870224-26.Exam Results:Seven Senior Operator Candidates Passed All Portions of Exams.One Candidate Failed All Portions IR 05000286/19860181986-08-25025 August 1986 Exam Rept 50-286/86-18OL on 860813.Exam Results:One Senior Reactor Operator Candidate Examined & Received License IR 05000286/19860121986-07-16016 July 1986 Requalification Program Evaluation Rept 50-286/86-12 on 860603-05.Exam Results:Three Senior Reactor Operators & Two Reactor Operators Passed Exams Resulting in Overall Program Evaluation of Satisfactory IR 05000286/19860051986-05-0909 May 1986 Exam Rept 50-286/86-05 on 860310-14.Exam Results:Five Senior Reactor Operators Passed & Two Failed IR 05000247/19850281986-01-28028 January 1986 Exam Rept 50-247/85-28 on 851209-13.Exam Results:All Candidates Passed All Portions of Exam IR 05000247/19850161985-08-22022 August 1985 Exam Rept 50-247/85-16 on 850709-11.Exam results:11 Candidates Passed & 1 Failed IR 05000286/19850061985-06-11011 June 1985 Operator Licensing Exam Rept 50-286/85-06 on 850423-26.Exam Results:Candidates Passed Operating Exam.One Senior Reactor Operator Candidate Failed Written Exam 1987-04-12
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000003/19980191999-03-0909 March 1999 Insp Rept 50-003/98-19 on 981130-990222.No Violation Noted. Major Areas Inspected:Review of Facility Mgt & Control ML20237D1381998-08-19019 August 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Between 971024 & 980528,licensee Failed to Assure That Design Change in Oct 1997 Subject to Design Control Measures ML20236M6011998-07-0606 July 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000.Violation Noted:On 970808,double Verifications of Steps 3.4.1 & 3.5.2 of PT-W1,which Involved Checks of DG Compressor,Not Performed,But Records Created ML20154Q1951998-01-22022 January 1998 Partially Deleted Investigation Rept 1-97-038.Noncompliance Noted.Major Areas Investigated:Falsification of Surveillance Test Records by Nuclear Production Technician ML20217H3531997-10-0707 October 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000.Violation Noted:Con Edison Did Not Operate within Restrictions of TS Figure 3.1.A-3,in That Pressurizer Level Was Greater than 30% PNO-I-97-053, on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR1997-08-22022 August 1997 PNO-I-97-053:on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR ML20217R3361997-08-19019 August 1997 NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Measures Were Not Established to Assure That Applicable Regulatory Requirements & Design Basis,Were Correctly Translated Into EOPs IR 05000247/19930261993-11-23023 November 1993 Insp Rept 50-247/93-26 on 931108-12.No Violations Noted. Major Areas Inspected:Mgt Support Plans,Protected & Vital Area Physical Barriers,Detection & Assessment Aids,Protected & Vital Area Access Control of Personnel IR 05000286/19930161993-10-19019 October 1993 Insp Rept 50-286/93-16 on 930802-06 & 0920-24.No Violations Noted.Major Areas Inspected:Isi Program,Procedures,Scope of ISI Work for Outage,Current Insp Plan & Testing Procedures IR 05000286/19930211993-09-17017 September 1993 Insp Rept 50-286/93-21 on 930830-0902.No Violations Noted. Major Areas Inspected:Mgt Support & Audits,Protected & Vital Area Physical Barriers,Detection & Assessment Aids & Protected Vital Area Access Control of Personnel PNO-I-90-094, on 901016,transfer of Fuel Assemblies Stuck in Upper Core Internals.No Apparent Damage to Dropped Fuel Assembly Occurred.Recovery Operations Secured1990-10-17017 October 1990 PNO-I-90-094:on 901016,transfer of Fuel Assemblies Stuck in Upper Core Internals.No Apparent Damage to Dropped Fuel Assembly Occurred.Recovery Operations Secured PNO-I-90-077, on 900906,unplanned Shutdown Greater than 48 H Occurred Due to RCS Packing Leak from Pressurizer Spray Valve.Plant Placed in Hot & Cold Shutdown.Licensee Activities Monitored & State of Ny Informed1990-09-0707 September 1990 PNO-I-90-077:on 900906,unplanned Shutdown Greater than 48 H Occurred Due to RCS Packing Leak from Pressurizer Spray Valve.Plant Placed in Hot & Cold Shutdown.Licensee Activities Monitored & State of Ny Informed PNO-I-90-065, on 900814,licensee Reported That Licensed Reactor Operator Tested Positive for Marijuana as Result of Random Fitness for Duty Test.Operator Unescorted Site Access Suspended for 14 Days1990-08-15015 August 1990 PNO-I-90-065:on 900814,licensee Reported That Licensed Reactor Operator Tested Positive for Marijuana as Result of Random Fitness for Duty Test.Operator Unescorted Site Access Suspended for 14 Days PNO-I-90-063, on 900809,plant Shutdown Due to Potential Loss of Three Emergency Diesel Generators.Caused by Blown Control Power Fuse.Fuse Replaced1990-08-0909 August 1990 PNO-I-90-063:on 900809,plant Shutdown Due to Potential Loss of Three Emergency Diesel Generators.Caused by Blown Control Power Fuse.Fuse Replaced ML20247K5281989-09-14014 September 1989 EN-89-086:on 890919,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 Will Be Issued to Licensee Based on Security Violations Re Access Control & Illumination in Protected Area ML20247B9531989-08-24024 August 1989 Enforcement Conference Rept 50-286/89-15 on 890808.Major Areas Discussed:Security Program During Spring 1989 Plant Outage IR 05000286/19890151989-07-24024 July 1989 Partially Withheld Physical Security Insp Rept 50-286/89-15 on 890605-07 (Ref 10CFR73.21).Violations Noted Re Physical Barriers,Vital Areas & Access Controls.Major Areas Inspected:Detection & Assessment Aids & Alarm Stations ML20245G2181989-06-21021 June 1989 PNS-I-89-010:on 890621,Dept of Investigation in New York City Received Call Threatening Destruction of Plant & Ref 1977 Incident Where Damage Inflicted on Plant.Bomb Threat Contingency Procedures Implemented & Security Maintained IR 05000286/19890031989-06-13013 June 1989 Enforcement Conference Rept 50-286/89-03 on 890428 in King of Prussia,Pa Re Findings of Insp Repts 50-286/89-03 & 50-286/88-22.Violations Noted.Areas Discussed:Security Program During Current Outage ML20247A1051989-05-0909 May 1989 Notice of Violation from Insp on 890228-0417.Violation Noted:Technicians Failed to Secure Pump When Vibration Level Observed on Pump Motor Exceeded Procedural Limit of 3.5 Mils ML20247A0681989-05-0505 May 1989 Notice of Violation from Insp on 890314-25.Violation Noted: Workers Allowed to Enter High Radiation Areas W/O Being Provided or Accompanied by Individual Authorized in Radiation Protection Procedures IR 05000286/19890051989-04-11011 April 1989 Partially Withheld Physical Security Insp Rept 50-286/89-05 on 890227-0303 (Ref 10CFR73.21).Violations & Noncompliances Noted.Major Areas inspected:non-routine Event,Mgt Support, Security Program Plans & Audits & Physical Barriers ML20154Q7231988-09-21021 September 1988 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000.Violations Noted:Qualification of Containment high-range Radiation Monitors Cable Connector Assembly Deficient PNO-I-88-065, on 880617,unit Tripped Due to High Water Level in Steam Generator 22.Caused by Contractor Cleaner Inadvertently Activating Boiler Feed Pump.Licensee Elected to Enter Cold Shutdown to Repair Connoseals1988-06-20020 June 1988 PNO-I-88-065:on 880617,unit Tripped Due to High Water Level in Steam Generator 22.Caused by Contractor Cleaner Inadvertently Activating Boiler Feed Pump.Licensee Elected to Enter Cold Shutdown to Repair Connoseals IR 05000247/19880121988-05-24024 May 1988 Physical Security Insp Rept 50-247/88-12 on 880407.No Noncompliance Noted.Major Areas Inspected:Program for Protection of Safeguards Info,Per 10CFR73.21,including Use of Required Storage Repositories & Handling Procedures IR 05000286/19880061988-05-19019 May 1988 Physical Security Insp Rept 50-286/88-06 on 880412-14.No Noncompliance Noted.Major Areas Inspected:Plan & Implementing Procedures,Organization,Program Audits,Testing & Maint,Physical Barriers & Security Sys Power Supply PNO-I-88-003, on 880101,steam Generator (SG) 23 Boiled Dry During Plant Heatup.Cause Not Stated.On 880104,station Mgt Started Evaluating Safety Significance of Event & Best Method to Refill Generator.Sg 23 Refilled on 8801051988-01-0707 January 1988 PNO-I-88-003:on 880101,steam Generator (SG) 23 Boiled Dry During Plant Heatup.Cause Not Stated.On 880104,station Mgt Started Evaluating Safety Significance of Event & Best Method to Refill Generator.Sg 23 Refilled on 880105 IR 05000286/19870131987-08-21021 August 1987 Safety Sys Outage Mod Insp Rept 50-286/87-13 on 870422-0714. Rept Describes Activities & Findings Associated W/First Portion of Team Insp Re Outage Design Insp IR 05000247/19870141987-06-0808 June 1987 Emergency Preparedness Insp Rept 50-247/87-14 on 870512-14. No Violations Identified.Major Areas Inspected:Licensee Annual Emergency Exercise Performed on 870513 IR 05000286/19870111987-05-14014 May 1987 Insp Rept 50-286/87-11 on 870420-24.No Violations Noted. Major Areas Inspected:Radiological Effluents Control Program,Mgt Controls,Air Cleaning Sys,Program Implementation & Previously Identified Items IR 05000286/19870091987-05-11011 May 1987 Insp Rept 50-286/87-09 on 870402-03.No Violations Noted. Major Areas Inspected:Nuclear Matl Control & Accounting, Including Organization & Operating,Shipping & Receiving, Storage & Internal Control & Records & Repts PNO-I-87-039, on 870430,licensee Identified Potential Circuit Failure Preventing Automatic Start of Auxiliary Feedwater Pumps by Loss of Main Feedwater or lo-lo Steam Generator Signals.Circuit Modified for Independent Relays1987-05-0101 May 1987 PNO-I-87-039:on 870430,licensee Identified Potential Circuit Failure Preventing Automatic Start of Auxiliary Feedwater Pumps by Loss of Main Feedwater or lo-lo Steam Generator Signals.Circuit Modified for Independent Relays IR 05000286/19870031987-04-12012 April 1987 Exam Rept 50-286/87-03OL on 870224-26.Exam Results:Seven Senior Operator Candidates Passed All Portions of Exams.One Candidate Failed All Portions PNO-I-87-025, on 870326,licensee Announced Plans to Shut Down Reactor on 870327 Due to Steadily Increasing Leakage on Reactor Coolant Pump Seal.Caused by Degraded Seal.Shutdown Expected to Last 10 Days1987-03-26026 March 1987 PNO-I-87-025:on 870326,licensee Announced Plans to Shut Down Reactor on 870327 Due to Steadily Increasing Leakage on Reactor Coolant Pump Seal.Caused by Degraded Seal.Shutdown Expected to Last 10 Days IR 05000286/19870021987-03-18018 March 1987 Insp Rept 50-286/87-02 on 870127-29.No Violations Noted. Major Areas Inspected:Dosimetry Staffing & Training, Facilities & Equipment Procedures,Dose Assessment QA & Documentation & Recordkeeping IR 05000247/19870041987-03-16016 March 1987 Insp Rept 50-247/87-04 on 870203-0302.No Violations Noted. Major Areas Inspected:Routine Daily Insps,As Well as Unscheduled Backshift Insps of Onsite Activities,Operations, Maint,Surveillance & Review of Periodic & Special Repts ML20207S3401987-03-11011 March 1987 Notice of Violation from Insp on 870127-29 IR 05000247/19870021987-03-10010 March 1987 Insp Rept 50-247/87-02 on 870127-29.Violation Noted:Failure to Include Acceptance Limits for Battery Electrolyte Temp & Failure to Ensure Battery Room Temp within Normal Bounds ML20207R1791987-03-0606 March 1987 PNS-I-87-003:on 870306,security Officer at Offsite Training Ctr in Toddville,Ny Received Bomb Threat by Telephone.Search of Site Produced Negative Results.Local Law Enforcement Agencies Responded.Security Measures Heightened IR 05000286/19870011987-03-0505 March 1987 Insp Rept 50-286/87-01 on 870106-0217.Major Areas Inspected: Plant Operations Including Shift Logs & Records,Reactor Trips/Engineered Safeguards Actuation,Surveillance,Maint & Followup to Generic Ltr 83-28 & TMI Action Items ML20212J3921987-03-0202 March 1987 Notice of Violation from Insp on 870106-0202 IR 05000247/19870011987-02-26026 February 1987 Insp Rept 50-247/87-01 on 870106-0202.Violation Noted:No post-maint (Mod) Test Performed After Changing Location of Emergency Diesel Generator Svc Water Flow Indication & Control Instruments PNO-I-87-010, on 870211,reactor Scrammed from Full Power During Transient Initiated by Loss of Instrument Bus.Safety Injection Signal Received on High Steam Flow Coincident W/Low Steam Line Pressure.Plant Stabilized in Hot Shutdown1987-02-12012 February 1987 PNO-I-87-010:on 870211,reactor Scrammed from Full Power During Transient Initiated by Loss of Instrument Bus.Safety Injection Signal Received on High Steam Flow Coincident W/Low Steam Line Pressure.Plant Stabilized in Hot Shutdown ML20210V6021987-02-10010 February 1987 Notice of Violation from Insp on 861215-19 IR 05000286/19860241987-02-0909 February 1987 Insp Rept 50-286/86-24 on 861215-19.Violation Noted:Raychem Splices Identified W/Less than Required 2-inch Overlap & Bending Radii Less than Allowed IR 05000247/19860331987-01-27027 January 1987 Radiation Protection Insp Rept 50-247/86-33 on 861215-19.No Violations Noted.Major Areas Inspected:Alara,Internal Exposure Control & External Exposure Control ML20213A4821987-01-22022 January 1987 Notice of Violation from Insp on 861116-870105 IR 05000247/19861361987-01-21021 January 1987 Meeting Rept 50-247/86-136 on 861209.Major Items Discussed: Plans for Integrated Assessment of Auxiliary Feedwater Sys. Mods Being Considered Include Providing Direct Indication of Overspeed Trip Mechanism Status in Control Room ML20212K3521987-01-20020 January 1987 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 Based on 860811-0922 Insp.Violation Noted:Reactor Heated Up Above 200 F W/Both Recirculation & Containment Spray Pumps Inoperable IR 05000286/19860231987-01-15015 January 1987 Onsite Regular & Backshift Insp Rept 50-286/86-23 on 861118- 870105.Violation Noted:Failure to Follow Administrative Procedures AP-6 & AP-25-3 Re Work Requests & Matl Substitutions,Respectively 1999-03-09
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U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 87-03 (0L) '
l FACILITY DOCKET NO. 50-286 1 I
FACILITY LICENSE NO. OPR-64 LICENSEE: Power Authority of New York P.O. Box 215 Buchanan, New York 10511 l
FACILITY: Indian Point Unit 3 EXAMINATION DATES: February 24-26, 1987 CHIEF EXAMINER: ht/O. N m_
Robert R. Temp " 4- F- 67 i Date Reactor Engi Examiner !
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REVIEWED BY: h)
Robert M. Keller, Chief 'Ntv[N
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Projec s ecti o. 1C APPROVED BY: C William F.'Kane, Director, DRP F/c/8[
Date SUMMARY:
Oral, candidate senior operator written and simulator examinations were administered to eight I
tions of their examinations and will be issued licenses.Seven senior operator ca!
One senior operator candidate failed all portions of the examinatio i j
PDR8705050029 870420 V ADOCK 05000286 PDR
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REPORT DETAILS TYPE OF EXAM: Replacement X EXAM RESULTS:
l l SR0 l 1 l l l Pass / Fail i I I I I I I I I I I I I I l Written Exam l I 7 / 1 l l l l l l 1 I I I I I I I I 10ral Exam l l 7 / 1 l 1 l I I I I I I I I I I I I l Simulator Examl 1 7 / 1 l l l l 1 I I I I l l I I I I 10verall l I 7 / 1 l 1 1 1 1 1 I I I I I I I I i CHIEF EXAMINER AT SITE: R.R. Temps, NRC OTHER EXAMINERS: N. Dudley, NRC E. Yachimiak, NRC G. Weale, Sonalysts (NRC Contractor Examiner) No generic weaknesses were noted during conduct of the Operating and Simulator Examination . Generic weaknesses noted from grading of the written examinations:
These comments are provided for your use in upgrading future requalifi-cation and initial operating training programs. No reply is necessar Most candidates did not list peak overlap as one of the three effects which cause the Doppler Temperature Coefficient to become less negative as fuel temperature increase Most candidates stated that the SG Atmospheric Dump Valves remain functional when instrument air pressure is less than 30 psi Per Off Normal Operating Procedure IA-1, the valves fail shu All candidates were unable to properly list the immediate action substeps for verification of main fees.ater isolatio . .
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. All candidates were unable to properly list the three isolation steps, and the basis for each, as found in ECA 0.0 for the RCP seal Most candidates had trouble listing the five parameters and/or trends these parameters should exhibit to indicate that natural circulation flow is in effec All but one candidate were unable to state the three individuals (by title) who may authorize a volunteer rescuer to receive exposure during extreme conditions involving life saving circumstance . Training and Reference Material: Significant problems were noted as to the accuracy and completeness of the System Descriptions. Several chapters of the System Descrip-tions were incomplete (i.e. pages missing), some did not reflect plant modifications and others referenced old emergency procedures no longer in effec Some inconsistencies were noted between information found in the E0P lesson plans and the E0P's themselve . Examination Meetings; Entrance, Exam Review and Exit: Entrance Meeting 1) Personnel Present at Entrance Meeting:
!!RC Richard Barkley Resident Inspector, IP-3 Noel Dudley Lead Reactor Engineer Examiner Robert Temps Reactor Engineer Examiner Gary Weale Licensing Examiner (Sonalysts)
Ed Yachimiak Reactor Engineer Facility Personnel Steve Bridges Operations Training Supervisor Michael Cass Assistant to Resident Manager William Josiger Resident Manager Bryan Ray Training Coordinator Richard Robenstein Training Consultant Richard Tansky Training Superintendent 2) An entrance meeting was held on February 24, 1987 to inform facility personnel of the purpose of the examination trip and to discuss any facility questions regarding the examination proces i
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The facility licensee expressed concern on two subject The first dealt with the extent of simulator scenarios, specifically operation of the plant outside of its design basis, and the second dealt with whether or not the NRC has guidelines which cover the extent to which simulator scenarios are take The NRC addressed the first concern by stating that the matter has already been addressed by the Commission in the proposed rule change to 10 CFR Part 55, dealing with degree requirements on shif NRC policy is that it is necessary, at times, to use simulator scenarios which operate the plant outside of its design basis in order to evaluate the effectiveness of the operator candidates in dealing with the situation and their ability to use and transition through the E0P' Regarding the second concern, guidelines in the Examiner Standards (NUREG-1021, ES-302) are used in the development of simulator scenarios. These guidelines are undergoing continuous upgrading and review based on licensee comments, examination development programs and usag B. Written Examination Review A review of the written examination was conducted following the exam. Four facility comments were discussed and all were re-solved at the examination review. As a result, the following changes were made to the answer key:
' Part (a) of question 5.09 was deleted as it dealt with theoretical concepts beyond those required to be used by SR0's. Any value obtained in part (a) was allowed to be used in part (b) and full credit given for determining subcooled margin, provided the correct process was use Point value of the question was reduced accordingl The response to part (e) of question 6.01 was changed to
"NO" as recent plant modifications removed any automatic actions associated with process radiation monitor R-17A/ Also, part (c) was modified to delete reference to the auto start of the dilution fan. Point value of the question was reduced accordingl i
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e nt nes hel d Supent n at nt wethendu ef mpr ion s a the ri of Por Ma n visor fa cted Exa ove nd ev age ov mi ed, al e nte ower r exaakn es cili er ner accur ni n nde a min se ty the re the siong a g of nt cka at s er li ai ge io w pr vi tu wi cy ni s ns e n e ew at th of F ion faebr censee vio ed ng Dindic, and oted , theus the ci ulary n w u f the Tr or f ai i ty r 26 Exa epa ated that du ri fee a rtm utu min e nt nya si if ng cili sub the ty mber In a r
ning Dep e ef,1987 er ation w o uld gni se si was spo type r e nd exa a ence T a fi que mul min rtme he nd be c inf nse An iant nt nfor ge reato r orm to of ati nnts. 's o
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, The answer to question 8.06 was modified to accept infor-mation contained in 10 CFR 50.74, parts X, Y and Z with full credit given provided the proper reference was mad The answers to question 8.08 were expanded as follows; for part (a), E plan classification III.3 was added and for part (c), classification I.A.5 was adde . The concern over completeness and accuracy of facility reference materials was discussed with the Training Department following the exam review and a copy of noted discrepancies was also sup-plied. As a result of the discussion, the facility has com-mitted to implement measures so that reference materials sent to the NRC for future examinations will be complete, accurate and up-to-dat Exit Meeting 1) Personnel Present at Exit Meeting:
NRC Richard Barkley Resident Inspector, IP-3 Noel Dudley Lead Reactor Engineer Examiner Robert Temps Reactor Engineer Examiner Ed Yachimiak Reactor Engineer Facility Personnel Steve Bridges Operations Training Supervisor Michael Cass Assistant to Resident Manager Bryan Ray Training Coordinator Joseph Russell Superintendent of Power Richard Tansky Training Superintendent 2) An exit meeting was held the evening of February 26, 1987. The matter of completeness and accuracy of facility reference materials was mentioned, along with the Training Department's commitment to improve the situation for future examination The Chief Examiner reviewed the number and type of examinations conducted over the previous week. In response to a question by the facility licensee, the facility was informed that no generic weaknesses were noted during the simulator / oral portions of the examinations, and that if subsequent review of the examination packages indicated any significant generic weaknesses the l Training Department would be informe j Attachment: Written Examination and Answer Key I