NRC Operator Licensing Retake Exam Repts 50-280/99-302 & 50-281/99-302 for Retake Exam Tests Administered on 990824. Exam Results:One SRO Candidate Received Part B re-take Operating Exam & PassedML20216F148 |
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Surry |
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09/08/1999 |
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NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
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ML20216F141 |
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50-280-99-302, 50-281-99-302, NUDOCS 9909210131 |
Download: ML20216F148 (6) |
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Category:EXAMINATION REPORT
MONTHYEARIR 05000280/19993021999-09-0808 September 1999 NRC Operator Licensing Retake Exam Repts 50-280/99-302 & 50-281/99-302 for Retake Exam Tests Administered on 990824. Exam Results:One SRO Candidate Received Part B re-take Operating Exam & Passed IR 05000280/19993011999-05-14014 May 1999 NRC Operator Licensing Exam Repts 50-280/99-301 & 50-281/99-301 (Including Completed & Graded Exams) for Tests Administered on 990329-0401 & 990412-15 IR 05000280/19933001993-10-20020 October 1993 Exam Repts 50-280/93-300 & 50-281/93-300 on 930920-24.Exam Results:Three SROs Passed Exam & One Out of Four ROs Failed Exam ML20209E1721987-03-30030 March 1987 Exam Rept 50-280/OL-87-01 Administered on 870209-11.Exam Results:Two Reactor Operators & Three Senior Reactor Operators Passed Exams.Written Exam & Answer Key Encl ML20215N1781986-10-10010 October 1986 Exam Rept 50-280/OL-86-01 of Exam Administered on 860721-30, for Units 1 & 2.Exam results:14 Candidates Passed Simulator exam,17 Candidates Passed Oral Exam & 10 Passed Written Exam IR 05000282/19860011986-06-23023 June 1986 Exam Repts 50-282/86-01 & 50-306/86-01 on 860519-23.Exam Results:One Reactor Operator & Four of Five Senior Reactor Operator Candidates Passed Exams ML20151T5041986-01-22022 January 1986 Exam Rept 50-280/OL-85-02 on 851204-06.Exam results:12 Operators Passed Operating Exam & 8 Operators Passed Written Exam.Written Exam Questions,Answer Key & Requalification Program Evaluation Rept Encl ML20126M0411985-05-0303 May 1985 Exam Rept 50-280/OL-85-01 on 850408-11.Exam Results:All 10 Candidates Passed 1999-09-08
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000280/19993021999-09-0808 September 1999 NRC Operator Licensing Retake Exam Repts 50-280/99-302 & 50-281/99-302 for Retake Exam Tests Administered on 990824. Exam Results:One SRO Candidate Received Part B re-take Operating Exam & Passed IR 05000280/19993011999-05-14014 May 1999 NRC Operator Licensing Exam Repts 50-280/99-301 & 50-281/99-301 (Including Completed & Graded Exams) for Tests Administered on 990329-0401 & 990412-15 IR 05000280/19980051998-07-13013 July 1998 Insp Repts 50-280/98-05 & 50-281/98-05 on 980503-0613.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000280/19970111997-10-0707 October 1997 Partially Withheld Insp Repts 50-280/97-11 & 50-281/97-11 on 970924 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Plant Support by Regional Safeguards Specialist ML20216B2581997-08-29029 August 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Licensee Failed to Monitor Performance & Establish Goals Commensurate W/Safety for Emergency Switch Gear Heating Ventilation PNO-II-93-062, on 931115,Unit 2 Tripped from 95% Reactor Power.Caused by Three Main Feedwater Regulating Valves Closed.Unit Has Been Taken to cold-shutdown to Investigate Cause of SG Level Oscillations1993-11-16016 November 1993 PNO-II-93-062:on 931115,Unit 2 Tripped from 95% Reactor Power.Caused by Three Main Feedwater Regulating Valves Closed.Unit Has Been Taken to cold-shutdown to Investigate Cause of SG Level Oscillations IR 05000280/19933001993-10-20020 October 1993 Exam Repts 50-280/93-300 & 50-281/93-300 on 930920-24.Exam Results:Three SROs Passed Exam & One Out of Four ROs Failed Exam PNO-II-93-037, on 930820,unscheduled Shutdown in Excess of 72 H Occurred Due to Need to Repair Leak in Joint on SG B. RCS Temp Reduced Below 200 Degrees F.Licensee to Inspect Drain Valve Assemblies on Sg.State of VA Notified1993-08-23023 August 1993 PNO-II-93-037:on 930820,unscheduled Shutdown in Excess of 72 H Occurred Due to Need to Repair Leak in Joint on SG B. RCS Temp Reduced Below 200 Degrees F.Licensee to Inspect Drain Valve Assemblies on Sg.State of VA Notified IR 05000280/19910221991-08-23023 August 1991 Insp Repts 50-280/91-22,50-281/91-22,50-338/91-18 & 50-339/91-18 on 910731 & 0801-02.No Violations Noted.Major Areas Inspected:Evaluation of Licensee Pipe Wall Thinning Insp & Replacement Program IR 05000280/19910151991-07-0808 July 1991 Insp Repts 50-280/91-15 & 50-281/91-15 on 910520-22 & 0619. No Violations Noted.Major Areas Inspected:Isi Including Observation of Visual & Nondestructive Exams on Main Steam Sys Piping Welds IR 05000280/19910091991-04-17017 April 1991 Insp Repts 50-280/91-09 & 50-281/91-09 on 910326-29.No Violations Noted.Major Areas Inspected:Audits & Appraisals, Training & Qualifications External Exposure Control,Control of Radioactive Matl & Contamination IR 05000280/19910061991-04-12012 April 1991 Insp Repts 50-280/91-06 & 50-281/91-06 on 910224-0330. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Surveillance,Procedures,Esf Sys Walkdown & Review of Licensee Self Assessment Capabilities ML20128Q5421991-04-12012 April 1991 Notice of Violation from Insp on 910224-0330.Violation Noted:Periodic Surveillance 2-PT-18.61 & PT-53.3 Were Not Performed within TS Period City Requirements PNO-II-90-066, on 901023,util Made 1 H Rept Per 10CFR50.72 Re Entry Into Station Emergency Plan for Shutdown of Unit 2. Caused by Svc Water Flow,Less That Design Basis Required Flow.Licensee Currently Evaluating Situation1990-10-23023 October 1990 PNO-II-90-066:on 901023,util Made 1 H Rept Per 10CFR50.72 Re Entry Into Station Emergency Plan for Shutdown of Unit 2. Caused by Svc Water Flow,Less That Design Basis Required Flow.Licensee Currently Evaluating Situation IR 05000280/19900231990-08-24024 August 1990 Partially Withheld Insp Repts 50-280/90-23 & 50-281/90-23 on 900723-27 (Ref 10CFR 2.790(d)).Major Areas Inspected: Review of Procedures,Records,Operations & Physical Inventory for Use,Control & Accountability of SNM PNO-II-89-066A, updates Status of Hurricane Hugo for Nuclear Facilities in Southeast.Manning of Incident Response Ctr by Region II Continuing1989-09-21021 September 1989 PNO-II-89-066A:updates Status of Hurricane Hugo for Nuclear Facilities in Southeast.Manning of Incident Response Ctr by Region II Continuing IR 05000280/19880501989-01-11011 January 1989 Partially Withheld Insp Repts 50-280/88-50 & 50-281/88-50 on 881212-16 (Ref 10CFR2.790(d) & 73.21).No Violations or Deviations Noted.Major Areas Inspected:Physical Security Program,Mgt Support,Plans,Audits,Barriers & Assessment IR 05000280/19880401988-10-26026 October 1988 Insp Repts 50-280/88-40,50-281/88-40,50-338/88-28 & 50-339/88-28 on 880926-30.No Violations or Deviations Noted. Major Areas Inspected:Control Room Habitability & Insp Followup Items ML20155F5031988-06-0808 June 1988 EN-88-048:notifies of Intent to Issue Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000 to Util,Based on Number of Violations,Including Failure to Adequately Evaluate Radiation Hazards Re Incore Detector ML20155F5801988-06-0808 June 1988 EN-88-047:on 880613,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 Will Be Issued to Licensee.Action Based on Failure to Verify Boric Acid Piping Heat Tracing Circuits on Monthly Basis PNO-II-88-011, on 880206,slight Positive Pressure Created in Primary Drain Tank Due to Large Vol of Water & Overhead Gas Compressor Inoperable,Causing Gaseous Leak in Auxiliary Bldg.Cause Not Stated1988-02-0808 February 1988 PNO-II-88-011:on 880206,slight Positive Pressure Created in Primary Drain Tank Due to Large Vol of Water & Overhead Gas Compressor Inoperable,Causing Gaseous Leak in Auxiliary Bldg.Cause Not Stated PNO-II-87-078, on 871126,licensee Removed Unit 1 from Svc to Repair Leaking Manway Cover on Secondary Side of C Steam Generator.Unit Cooled Down & Manway Gasket Replaced. Commonwealth of Virginia Informed1987-11-30030 November 1987 PNO-II-87-078:on 871126,licensee Removed Unit 1 from Svc to Repair Leaking Manway Cover on Secondary Side of C Steam Generator.Unit Cooled Down & Manway Gasket Replaced. Commonwealth of Virginia Informed PNO-II-87-061, on 870920,automatic Trip from 100% Power Occurred.Caused by Phase to Ground Fault in B Phase at Electrical Connection on B Reactor Coolant Pump.Safety Injection Signal Reset1987-09-21021 September 1987 PNO-II-87-061:on 870920,automatic Trip from 100% Power Occurred.Caused by Phase to Ground Fault in B Phase at Electrical Connection on B Reactor Coolant Pump.Safety Injection Signal Reset PNO-II-87-053A, on 870730,State of Ny,Dept of Environ Conservation & Dept of Radiation Health Completed Survey of Miscellaneous Boxes & Equipment W/Markings from VEPCO Found in Abandoned Bldg in Springwater,Ny.No Problems Noted1987-07-30030 July 1987 PNO-II-87-053A:on 870730,State of Ny,Dept of Environ Conservation & Dept of Radiation Health Completed Survey of Miscellaneous Boxes & Equipment W/Markings from VEPCO Found in Abandoned Bldg in Springwater,Ny.No Problems Noted PNO-II-87-053, on 870728,licensee Notified That Fireman Discovered Miscellaneous Boxes & Equipment in Abandoned Bldg Outside Springwater,Ny.Matl Might Be Clean Surplus Matl Disposed of After Cancellation of North Anna 31987-07-29029 July 1987 PNO-II-87-053:on 870728,licensee Notified That Fireman Discovered Miscellaneous Boxes & Equipment in Abandoned Bldg Outside Springwater,Ny.Matl Might Be Clean Surplus Matl Disposed of After Cancellation of North Anna 3 PNO-II-87-040, on 870623,unit Manually Shut Down Following Estimated 40 Gpm Leak in Rcs.Caused by Packing on Reactor Coolant Loop Stop Valve.Licensee Preparing Unit to Go to Mode 5 to Effect Repairs1987-06-23023 June 1987 PNO-II-87-040:on 870623,unit Manually Shut Down Following Estimated 40 Gpm Leak in Rcs.Caused by Packing on Reactor Coolant Loop Stop Valve.Licensee Preparing Unit to Go to Mode 5 to Effect Repairs IR 05000280/19870111987-06-22022 June 1987 Insp Repts 50-280/87-11 & 50-281/87-11 on 870427-0501.Three Potential Enforcement Findings Noted.Major Areas Inspected: Audit Performed in Feb 1987 by Util of Industrial Distributors PNO-II-87-037, on 870607,licensee Entered 24 H Limiting Condition for Operation When Outside Recirculation Spray Pump B Failed Periodic Surveillance Test Due to High Vibration & Low Discharge Pressure.Unit Shut Down1987-06-0909 June 1987 PNO-II-87-037:on 870607,licensee Entered 24 H Limiting Condition for Operation When Outside Recirculation Spray Pump B Failed Periodic Surveillance Test Due to High Vibration & Low Discharge Pressure.Unit Shut Down IR 05000280/19870091987-05-21021 May 1987 Insp Repts 50-280/87-09 & 50-281/87-09 on 870405-0502.No Violations Identified.Major Areas Inspected:Licensee Actions on Previous Enforcement Matters,Plant Operations,Maint & Surveillance & LER Review & 10CFR21 Reviews PNO-II-87-032, updates PNO-II-87-029.Util Determined That Partial Closure of Isolation Valve Which Brought About Reactor Scram on 870516 Caused by Shearing of Valve Stem Above Backseat.Metallurgist Evaluating Break1987-05-21021 May 1987 PNO-II-87-032:updates PNO-II-87-029.Util Determined That Partial Closure of Isolation Valve Which Brought About Reactor Scram on 870516 Caused by Shearing of Valve Stem Above Backseat.Metallurgist Evaluating Break PNO-II-87-029, on 870516,unit Tripped on Low Reactor Coolant Flow Rate in Loop A.Caused by Partial Closure of Hot Loop Isolation Valve.Outage of 12 Days Planned to Correct Problem.Resident Inspector Will Provide Followup1987-05-18018 May 1987 PNO-II-87-029:on 870516,unit Tripped on Low Reactor Coolant Flow Rate in Loop A.Caused by Partial Closure of Hot Loop Isolation Valve.Outage of 12 Days Planned to Correct Problem.Resident Inspector Will Provide Followup ML20209E1721987-03-30030 March 1987 Exam Rept 50-280/OL-87-01 Administered on 870209-11.Exam Results:Two Reactor Operators & Three Senior Reactor Operators Passed Exams.Written Exam & Answer Key Encl ML20205Q1481987-03-24024 March 1987 Notice of Violation from Insp on 870209-13 IR 05000280/19870031987-03-20020 March 1987 Insp Repts 50-280/87-03 & 50-281/87-03 on 870209-13. Violations Noted:Failure to Adhere to Radiation Control Procedures,To Comply W/Low Level Radwaste Disposal Facility Agreement State License Conditions & W/Dot Regulations IR 05000280/19870041987-03-0606 March 1987 Insp Repts 50-280/87-04 & 50-281/87-04 on 870201-28.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations,Maint,Surveillance,Licensee Action on Previous Enforcement Matters & TMI Action Item Closeout ML20207T5821987-03-0202 March 1987 Notice of Violation from Insp on 861113-20 & 870209 IR 05000281/19860361987-02-23023 February 1987 Insp Rept 50-281/86-36 on 861113-20 & 870209.Violations Noted:Failure to Properly Valve Penetrations for Type a Test in Accordance w/10CFR50,App J.Four Unresolved Items Identified PNO-II-87-011A, on 870213,leak Discovered in Svc Water Line Below Floor of Unit 2 Turbine Bldg.Util Will Replace Defective Portion of Unit 2 Side of Svc Water Piping.Unit 1 Side of Same Sys Tested & Acceptable1987-02-18018 February 1987 PNO-II-87-011A:on 870213,leak Discovered in Svc Water Line Below Floor of Unit 2 Turbine Bldg.Util Will Replace Defective Portion of Unit 2 Side of Svc Water Piping.Unit 1 Side of Same Sys Tested & Acceptable IR 05000280/19870021987-02-18018 February 1987 Insp Repts 50-280/87-02 & 50-281/87-02 on 870202-06.No Violations or Deviations Noted.Major Areas Inspected:Exam Onsite in Area of Info Notices,Unplanned Radiological Releases,Effluent Monitors & Effluent Reporting IR 05000280/19860411987-02-12012 February 1987 Insp Repts 50-280/86-41 & 50-281/86-41 on 861207-870131.No Violations or Deviations Noted.Major Areas Inspected:Action on Previous Enforcement Matters,Plant Operations,Maint & Surveillance & IE Bulletin Followup PNO-II-87-011, heatup of Unit 1 Beginning in Preparation for Return to Svc.Restart of Unit 2 Scheduled 2 to 3 Wks Later.Licensee Informed of Region II Acceptance of Restart Plan in 870210 Augmented Insp Team Rept1987-02-12012 February 1987 PNO-II-87-011:heatup of Unit 1 Beginning in Preparation for Return to Svc.Restart of Unit 2 Scheduled 2 to 3 Wks Later.Licensee Informed of Region II Acceptance of Restart Plan in 870210 Augmented Insp Team Rept ML20211C5161987-02-10010 February 1987 Augmented Insp Repts 50-280/86-42 & 50-281/86-42 on 861209- 870114.Violation Noted:Failure to Fully Follow Procedures, Provide Adequate Instruction for & Document Performance of Maint Operations IR 05000280/19860421987-02-10010 February 1987 Augmented Insp Repts 50-280/86-42 & 50-281/86-42 on 861209- 870114.Violation Noted:Failure to Fully Follow Procedures, Provide Adequate Instruction for & Document Performance of Maint Operations ML20211C4781987-02-10010 February 1987 Notice of Violation from Insp on 861209-870114 IR 05000280/19870011987-02-0404 February 1987 Insp Repts 50-280/87-01 & 50-281/87-01 on 870112-15.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection Sys Interaction Events Associated w/861209 Feedwater Pipe Rupture ML20212F9001987-01-0606 January 1987 Notice of Violation from Insp on 861020-23 & 27-31 IR 05000280/19860381986-12-29029 December 1986 Insp Repts 50-280/86-38 & 50-281/86-38 on 861102-1206.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance,Outages,Followup on Region Identified Items & Insp of Dry Spent Nuclear Fuel Facility IR 05000280/19860401986-12-23023 December 1986 Insp Repts 50-280/86-40 & 50-281/86-40 on 861129-1203.No Violations or Deviations Noted.Major Areas inspected:post- Refueling Startup Tests,Thermal Power Determination & RCS Leakage Measurements PNO-II-86-091D, licensee Repts Two Addl Deaths Occurred as Result of Injuries from 861209 Accident.Caused by Break of 18-inch Feedwater Sys Suction Line Scalding Eight Workers W/Hot Water & Steam.Number of Dead Now Four1986-12-16016 December 1986 PNO-II-86-091D:licensee Repts Two Addl Deaths Occurred as Result of Injuries from 861209 Accident.Caused by Break of 18-inch Feedwater Sys Suction Line Scalding Eight Workers W/Hot Water & Steam.Number of Dead Now Four PNO-II-86-091C, ultrasonic Testing of Unit 1 Piping Elbow Disclosed Min Pipe Wall Thickness of 0.16 Inch.Design Specs Require 0.36 Inch Min Thickness.Ultrasonic Testing Continuing1986-12-15015 December 1986 PNO-II-86-091C:ultrasonic Testing of Unit 1 Piping Elbow Disclosed Min Pipe Wall Thickness of 0.16 Inch.Design Specs Require 0.36 Inch Min Thickness.Ultrasonic Testing Continuing 1999-09-08
[Table view] |
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U. S. NUCLEAR REGULATORY COMMISSION REGION 11
Docket Nos.: 50-280, 50-281 !
License Nos.: DPR-32, DPR-37 l
Report Nos.: 50-280/99-302, 50-281/99-302 I
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Licensee: Virginia Electric and Power Company (VEPCO)
Facility: Surry Power Station, Units 1 & 2 Location: 5850 Hog Island Road Surry, VA 23883 Date: August 24,1999 Examiner: Richard S. Baldwin, Chief License Examiner Approved by: Harold O. Christensen, Chief )
Operator Licensing and Human 1 Performance Branch Division of Reactor Safety l
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Enclosure 1 9909210131 990908 PDR ADOCK 05000280 V PDR
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EXECUTIVE SUMMARY Surry Nuclear Power Station Units 1 & 2 NRC Examination Report Nos. 50-280/99-302 and 50-281/99-302 i
During August 24,1999, an NRC examiner conducted an announced operator licensing initial
. re-take examination in accordance with the guidance of Examiner Standards, NUREG-1021,
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Interim Revision 8. This examination implemented the operator licensing requirements of 10 CFR $55.45.
j One Senior Reactor Operator (SRO) candidate received a Part B re-take operating examinatio The operating test was administered by the NRC on August 24,199 Ooerations
The submitted operating test met the requirements of NUREG-1021. The licensee's submittal was considered satisfactory. (Section O5.1)
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The SRO candidate passed the examination. (Section 05.1) l
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Overall performance on the re-take operating test was satisfactory. (Section 05.1)
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Candidate Pass / Fail SRO RO Total Percent
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Pass 1 0 1 100 Fail 0 0 0 0
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- Report Details I, Operations 05 Operator Training and Qualifications 05.1 Initial Licensina Examinations Scope An NRC examiner conducited a regular, announced operator licensing initial re-take i examination on August 24,1999. The NRC examiner administered an examination developed by the licensee's training department, under the requirements of an NRC security agreement, in accordance with the guidelines of the Examiner Standards (ES),
NUREG-1021, Interim Revision 8. One Senior Reactor Operator upgrade (SRO(U))
received a Part B re-take operating examinatio Observations and Findinas
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The licensee developed the SRO Part B Job Performance Measure (JPM) set for use during this examination. All materials were submitted to the NRC on schedule. The NRC examiners reviewed, modified as necessary, and approved the examination prior to l administration. The NRC conducted an on-site preparation visit during the week of the examination to validate examination materials and familiarize themselves with the details ,
required for examination administratio Operating Test Development The NRC reviewed one Part B walkthrough examination submitted by the facility, for one SRO(U). This was comprised of three simulator and two in-plant JPMs. The examiner found the JPMs were developed at the appropriate level as described in NUREG-102 There were two JPM questions that were considered direct look-up which lacked operational validity. These questions were either changed or references were not allowed to answer these question Examination Results The NRC noted that the quality of the licensee's proposed examination was satisfactor The review of this operating re-take examination revealed the SRO candidate passed the
- examination. The examiner identified one weakness in candidate performance during the operations portion of the examination. Details of the weakness are described in the individual's examination report, Form ES-303-1, " Operator Licensing Examination l Report." Copies of the evaluation were forwarded under separate cover to the training t
. manager in order to enable the licensee to evaluate the weakness and provide appropriate remedial training for that operator, as necessary. In general, the weakness concerned the use of radiation adverse containment number .
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c. Conclusion The submitted examination met the requirements of NUREG-1021. The candidate passed the examination. Overall performance on the operating test was satisfactory.
l l V. Manaaement Meetinas X1. Exit Meeting Summary At the conclusion of the site visit, the examiners met with representatives of the plant staff listed on the following page to discuss the results of the examinations and other issues. No proprietary material was provided.
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PARTIAL LIST OF PERSONS CONTACTED
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Licensee: .
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M. Crist, Superintendent-Operations D. Dickey, Operations Instructor B. Garber, Licensing E. Grecheck, Site Vice President W. Henry, Shift Supervisor, Operations D. Llewellyn, Superintendent-Nuclear Training H. McCallum, Supervisor-Operations Training D. Modlin, Oversight Department -
E. Shore, Operations Instructor R. Simrnons, Operations Instructor M. Smith, Station Nuclear Safety J. Spence, Operations instructor K. Spencer, Operations instructor A. Stanley, Operations Instructor S. Stanley, Licensing T. Swindell, Radiation Protection NB.Q:
R. Musser, Senior Resident inspector, Surcy M. Sykes, Examiner, Rll ITEMS OPENED, CLOSED, AND DISCUSSED Opene None Closed None Discusant None
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l SIMULATION FACILITY REPORT Facility Licensee: Virginia Power - Surry Power Station Units 1 & 2 Facility Docket Nos.: 50-280 and 50-281 Operating Tests Administered on: August 24,1999 This form is to be used only to report observations. These observations do not constitute audit or inspection findings and are not, without further verification and review, indicative of noncompliance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information that may be used in future evaluations. No licensee action is required in response to these observation ]
j While conducting the simulator portion of the operating tests, the foilowing items were observed:
ITEM DESCRIPTION l There were no simulator fidelity problem l l
Enclosure 2
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