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Category:EXAMINATION REPORT
MONTHYEARIR 05000423/19970041997-08-12012 August 1997 Exam Rept 50-423/97-04(OL) on 970707-11.Exam Results:All RO & SRO Applicants Passed All Portions of Exams ML20134K1721997-02-0707 February 1997 NRC Operator Licensing Exam Rept 50-245/96-12 Administered on 961202-06.Exam Results:Six of Seven Applicants Failed Exams & One Passed,But License Was Not Issued Due to Required Plant Manipulations Not Being Completed IR 05000245/19930251993-10-0101 October 1993 Exam Rept 50-245/93-25-OL on 930914-16.Exam Results: Requalification Exams Were Administered to 8 ROs & 7 Sros. All 15 Licensed Operators Passed All Portions of Exam IR 05000336/19920331993-01-27027 January 1993 Requalification Exam Rept 50-336/92-33OL-RQ on 921214-17. Exam results:14 Licensed Operators Passed All Portions of Exam,Including Evaluation of Three Operating Crews. Requalification Program Determined to Be Satisfactory IR 05000423/19920251992-12-21021 December 1992 Exam Rept 50-423/92-25 (OL-RQ) on 921116-19.Exam Results: All Four Operators Passed Exams.Two SROs & ROs Operated Successfully as Crew During Two Simulator Scenarios.Results of Exam Combined W/Results of Previous Requalification Exam IR 05000245/19900101990-10-26026 October 1990 Exam Rept 50-245/90-10OL on 900827-31.Exam Results:Three of Five SROs & Three ROs Passed Operating & Written Tests IR 05000366/19900271990-10-15015 October 1990 Exam Rept 50-366/90-27OL on 901003.Exam Results:Reactor Operator Candidate Passed Written Exam & Issued Reactor Operator License on 901009 IR 05000336/19900101990-07-20020 July 1990 Requalification Program Audit Rept 50-336/90-10OL-RQ on 900618-22.Audit Results:Training Program Rated Satisfactory IR 05000423/19890051989-05-0303 May 1989 Exam Rept 50-423/89-05OL on 890321-23.Exam Results:All Candidates Successfully Completed Both Written & Operating Parts of Respective Exams Except for One Reactor Operator That Failed Section 1 of Written Exam IR 05000245/19880161989-03-17017 March 1989 Exam Rept 50-245/88-16OL on 881107-10.Exam Results:All Reactor Operator Candidates Passed Exams.Six Senior Reactor Operator (SRO) Candidates Passed Written Exam & Operating Test.One SRO Candidate Failed Written Exam IR 05000336/19880171988-09-12012 September 1988 Exam Rept 50-336/88-17OL Administered During Wk of 880718. Exam Results:Written & Operating Exams Administered to Three Senior Reactor Operator Upgrade Candidates.All Three Passed IR 05000336/19870311988-03-25025 March 1988 Exam Rept 50-336/87-31OL on 880111-14.Exam Results:Six Reactor Operators & Two Instant Senior Reactor Operators Passed Exam IR 05000423/19870281988-03-16016 March 1988 Exam Rept 50-423/87-28OL on 871214-18.Exam Results:Three Senior Reactor Operator (SRO) Candidates & Two Reactor Operator (RO) Candidates Passed Written/Operating Exams.One RO Candidate Failed Operating Exam & One SRO Failed Both IR 05000245/19870231987-11-19019 November 1987 Exam Rept 50-245/87-23OL on 870921-25.Exam Results:Five Senior Reactor Operators Passed Exams.Two Senior Reactor Operators Failed.Related Info Encl IR 05000423/19870231987-11-0606 November 1987 Requalification Exam Rept 50-423/87-23OL on 870612,0731 & 0904.Exam Results:All Senior Reactor Operators (Sros) & Reactor Operators (Ros) Passed Operating Portion of Exams. Three SROs & Two ROs Failed Written Exams IR 05000423/19870161987-10-0909 October 1987 Exam Rept 50-423/87-16OL on 870818-20.Exam Results:One Senior Reactor Operator Candidate Failed Written Exam & Two Failed Operating Exam IR 05000245/19860211987-03-12012 March 1987 Exam Rept 50-245/86-21OL on 861215-19.Exam Results:All Candidates Passed Exams.Accuracy of Simulator Cause & Malfunction Book & Number of Errors Found in Training Matl Raised Concern IR 05000336/19860251987-03-0404 March 1987 Requalification Program Audit Rept 50-336/86-25OL on 861113 & 870105-16.Audit Results:Evaluation of Facility Written Exam Grading & Overall Program Evaluation Satisfactory IR 05000423/19860311987-03-0303 March 1987 Exam Rept 50-423/86-31OL on 861215-19.Exam Results:Four Senior Reactor Operator (Sro),Seven Reactor Operator & One Instructor Certification Candidate Received Licenses. One SRO Failed Simulator Portion of Operating Exam IR 05000336/19860221987-02-0404 February 1987 Exam Rept 50-336/86-22OL on 861215.Exam Results:One Reactor Operator Candidate & One Senior Reactor Operator Candidate Passed Operating Exam.Both Issued Licenses IR 05000336/19860101986-09-15015 September 1986 Exam Rept 50-336/86-10OL on 860707-11.Exam Results:Seven Senior Reactor & Five Reactor Operator Licenses Issued.Two Candidates Failed Simulator Exam & One Candidate Failed Written Exam.Exam & Answer Key Encl IR 05000423/19860101986-07-0202 July 1986 Exam Rept 50-423/86-10 on 860331-0404.Exam Results:Three Reactor Operator & Six of Nine Senior Reactor Operator Candidates Passed All Portions of Exam.Problem Continues Re Lack of Proper Exam Security IR 05000423/19850451986-01-22022 January 1986 Exam Rept 50-423/85-45 on 851030-31.Exam Results:One Reactor Operator & Seven Senior Reactor Operator Candidates Passed IR 05000245/19850211985-12-0202 December 1985 Exam Rept 50-245/85-21 During Wk of 850812.Exam Results:One of Six Reactor Operator Candidates & One of Four Senior Reactor Operator Candidates Failed Both Written & Oral Exams.Supporting Documentation Encl IR 05000423/19850441985-11-13013 November 1985 Exam Rept 50-423/85-44(OL) on 850903-06 & 09-12.Exam results:11 Out of 14 Senior Reactor Operator & 3 Out of 4 Reactor Operator Candidates Passed All Portions of Exams & Will Be Issued Licenses ML20133M2181985-08-0202 August 1985 Exam Rept 50-423/OL-85-15 on 850514-17 & 21-23.Exam Results: Two Reactor Operators & Nine Senior Reactor Operators Passed.Three Reactor Operators & Seven Senior Reactor Operators Failed 1997-08-12
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000245/19990081999-09-14014 September 1999 Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations Noted & Being Treated as Ncvs. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000423/19990071999-08-27027 August 1999 Insp Rept 50-423/99-07 on 990614-0715.Violations Noted & Being Treated as Ncvs.Major Areas Inspected:Review of C/A Program Using IP 40500, Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000336/19990061999-07-19019 July 1999 Insp Repts 50-336/99-06 & 50-423/99-06 on 990420-0614.Ten Violations Occurred & Being Treated as non-cited Violations. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000336/19982191999-06-10010 June 1999 Insp Rept 50-336/98-219 on 981214-18,990126-29,0208-19 & 0301-05.Noncited Violations Identified.Major Areas Inspected:Exam of Licensee Corrective Action Implementation IR 05000245/19990051999-06-0404 June 1999 Errata to Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05,consisting of Figure 1 ML20207G1211999-06-0303 June 1999 Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05 on 990302-0419.No Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support ML20207F1521999-05-25025 May 1999 Notice of Violation from Investigation Rept 1-94-021 on 940506-960329.Violation Noted:Between 740831-910407,licensee Made Changes to Facility Described in Safety Analysis Rept for Refueling Core Offloads Without Performing Evaluation ML20196K2621999-05-24024 May 1999 EN-99-020:on 980525,notice of Violation & Exercise of Enforcement Discretion Will Be Issued to Licensee.Action Based on Severity Level III Problem Consisting of Four Individual Violations Involving Refueling Outage PNO-I-99-022, on 990509,Millstone Unit 2 Established Reactor Criticality.Nrc Staff Providing Augmented Insp Coverage of Restart Activities,Including round-the-clock Observations of Licensee Activities During Key Operational Evolutions1999-05-11011 May 1999 PNO-I-99-022:on 990509,Millstone Unit 2 Established Reactor Criticality.Nrc Staff Providing Augmented Insp Coverage of Restart Activities,Including round-the-clock Observations of Licensee Activities During Key Operational Evolutions IR 05000336/19990031999-05-10010 May 1999 Insp Rept 50-336/99-03 on 990322-26.No Violations Noted. Major Areas Inspected:Review of Actions Taken by Util to Resolve Significant Issues List Item 21,fire Protection ML20206F4601999-04-30030 April 1999 Insp Rept 50-336/99-04 on 990315-31.Violation Noted.Major Areas Inspected:Monitored Licensee Activities During Plant Transition Between Operational Modes,Both During Normal & off-normal Working Hours PNO-I-99-016, on 990406,operators Initiated Plant Cooldown from Normal Operating Pressure & Temp in Mode 3,hot Standby. Cooldown Was Necessary to Minimize Further Degradation of Bonnet Pressure Seal for Valve 2-SI-652 & to Repair Valve1999-04-0707 April 1999 PNO-I-99-016:on 990406,operators Initiated Plant Cooldown from Normal Operating Pressure & Temp in Mode 3,hot Standby. Cooldown Was Necessary to Minimize Further Degradation of Bonnet Pressure Seal for Valve 2-SI-652 & to Repair Valve ML20205M7201999-04-0606 April 1999 Notice of Violation from NRC OI Case 1-96-002 & Conclusions of Millstone Independent Review Team.Violation Noted. E Debarba,Deliberately Discriminated Against Supervisor in Performance Engineering Group at Millstone Station ML20205M7351999-04-0606 April 1999 Notice of Violation from Investigation in Case Numbers 1-96-002 & 1-97-007.Violation Noted:Licensee Discriminated Against Supervisor in Performance Engineering Group at Plant Due to Involvement in Protected Activities IR 05000245/19990021999-04-0202 April 1999 Insp Repts 50-245/99-02,50-336/99-02 & 50-423/99-02 on 990112-0301.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000336/19990011999-03-29029 March 1999 Insp Rept 50-336/99-01 on 990117-0217.Violations Noted.Major Areas Inspected:Licensee C/A Program Implementation Using Guidance of NRC IP 40500, Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems ML20205J0941999-03-12012 March 1999 Rept of Review of Millstone Units 1,2 & 3:Allegations of Discrimination in NRC Ofc of Investigations Cases 1-96-002, 1-96-007,1-97-007 & Associated Lessons Learned ML20207M1131999-03-0909 March 1999 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $88,000.Violation Noted:Employment of Two Contractor Employees Terminated in Aug 1997,in Part Because Individuals Raised Concerns Re MOV Program Manual ML20205G6161999-03-0909 March 1999 EN-99-010:on 990309,notice of Proposed Imposition of Civil Penalty in Amount of $88,000 Issued to Licensee.Action Based Upon Severity Level II Problem Involving Discrimination Against Two Contractor Employees at Millstone MOV Dept IR 05000245/19980061999-03-0101 March 1999 Insp Repts 50-245/98-06,50-336/98-06 & 50-423/98-06 on 981123-990111.No Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support PNO-I-99-006, on 990128,operators Inadvertently Reduced Spent Fuel Pool Water Level by Two Inches When Purification of Spent Fuel Pool Water Initiated.Operators Held Shift Briefing to Discuss Realigning Purification Sys1999-01-29029 January 1999 PNO-I-99-006:on 990128,operators Inadvertently Reduced Spent Fuel Pool Water Level by Two Inches When Purification of Spent Fuel Pool Water Initiated.Operators Held Shift Briefing to Discuss Realigning Purification Sys IR 05000245/19982171999-01-22022 January 1999 Evaluation Repts 50-245/98-217,50-336/98-217 & 50-423/98-217 Conducted on 981026-30.Areas Evaluated:Whether NNECO Has Improved Sufficiently & Has Demonstrated Sustained Performance in Maintaining safety-conscious Work Environ PNO-I-99-004, on 990115,carbon Dioxide Was Inadvertently Discharged Into Unit 3 Cable Spreading Room,Containing Electrical Wiring.Ambulance Reported to Site as Precautionary Measure.Licensee Assembled Event Review1999-01-20020 January 1999 PNO-I-99-004:on 990115,carbon Dioxide Was Inadvertently Discharged Into Unit 3 Cable Spreading Room,Containing Electrical Wiring.Ambulance Reported to Site as Precautionary Measure.Licensee Assembled Event Review IR 05000336/19980051999-01-0707 January 1999 Insp Repts 50-336/98-05 & 50-423/98-05 on 981006-1123. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20199C6381999-01-0707 January 1999 Notice of Violation from Insp on 981006-1123.Violation Noted:On or Before 981120,conduit 9-15,in Fire Area A-24,not Sealed & Tested in Accordance with Astme E-119,fire Endurance Test PNO-I-99-001, on 981231,Millstone Unit 2 Began Reloading Fuel Into Reactor After Extended Shutdown.Millstone Unit 3 Went Critical on 981230,after Forced Outage Due to Inadvertent MSIV Closure During Surveillance Testing at Power1999-01-0404 January 1999 PNO-I-99-001:on 981231,Millstone Unit 2 Began Reloading Fuel Into Reactor After Extended Shutdown.Millstone Unit 3 Went Critical on 981230,after Forced Outage Due to Inadvertent MSIV Closure During Surveillance Testing at Power PNO-I-98-062, on 981211,Millstone Unit 3 Tripped from 100% Reactor Power During MSIV Partial Stroke Testing.Solenoid Valve Integral to MSIV Failed to Reopen When Licensed Operator Released Test Switch1998-12-15015 December 1998 PNO-I-98-062:on 981211,Millstone Unit 3 Tripped from 100% Reactor Power During MSIV Partial Stroke Testing.Solenoid Valve Integral to MSIV Failed to Reopen When Licensed Operator Released Test Switch ML20195H6901998-11-18018 November 1998 Notice of Violation from Insp on 980818-1005.Violation Noted:Engineering Evaluations Not Performed When RCS Heatup Rate Limit Exceeded on 951217 & When RCS Cooldown Rate Limit Exceeded on Three occasions,940424,0728 & 951215 IR 05000245/19982161998-11-18018 November 1998 Insp Repts 50-245/98-216,50-336/98-216 & 50-423/98-216 on 980818-1005.Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support IR 05000336/19982031998-11-0505 November 1998 Insp Rept 50-336/98-203 on 980824-0904.No Violations Noted. Major Areas Inspected:Effectiveness of Configuration Mgt Plan ML20155B1521998-10-23023 October 1998 Notice of Violation from Insp on 980810-0903.Violation Noted:Design Basis,As Described in FSAR Chapter 14,Accident Analyses Had Not Been Correctly Translated Into Plant Procedures & Acceptance Criteria IR 05000336/19982131998-10-23023 October 1998 Insp Rept 50-336/98-213 on 980810-0903.Violations Noted. Major Areas Inspected:Certain Aspects of Accident Mitigation Sys IR 05000245/19982151998-10-14014 October 1998 Evaluation Repts 50-245/98-215,50-336/98-215 & 50-423/98-215 on 980824-28.Major Areas Evaluated:Whether Licensee Has Improved Sufficiently & Has Demonstrated Sustained Performance in Maintaining safety-conscious Work Environ IR 05000336/19980041998-10-0101 October 1998 Insp Rept 50-336/98-04 on 980914-18.No Violations Noted. Major Areas Inspected:Mov Program Associated with GL 89-10 IR 05000245/19982121998-09-25025 September 1998 Insp Repts 50-245/98-212,50-336/98-212 & 50-423/98-212 on 980630-0817.No Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support IR 05000423/19982111998-09-11011 September 1998 Insp Rept 50-423/98-211 on 980413-24,0511-15,27-29,0609-11 & 23-25.Violation Noted.Major Areas Inspected:Evaluation of Licensee C/As & Other ICAVP Process Activities ML20154D1151998-09-11011 September 1998 Notice of Violation from Insp on 980413-24-0511-15,27-29, 0609-11 & 23-25.Violation Noted:Program Implemented TS 6.8.4.a,failed to Include Provisions to Reduce Leakage from RSS Heat Exchangers to SW Sys IR 05000424/19980061998-09-10010 September 1998 Insp Repts 50-424/98-06 & 50-425/98-06 on 980628-0815.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support PNO-I-98-039, 980812,Millstone Unit 3 Was Shutdown to Repair Small Leak on Afws Discharge Noted.Current Leakage Does Not Exceed Regulatory Requirements & Shutdown Not Required by Tech Specs.Licensee Issued Press Release on 9808111998-08-12012 August 1998 PNO-I-98-039:980812,Millstone Unit 3 Was Shutdown to Repair Small Leak on Afws Discharge Noted.Current Leakage Does Not Exceed Regulatory Requirements & Shutdown Not Required by Tech Specs.Licensee Issued Press Release on 980811 ML20237D3041998-08-12012 August 1998 Notice of Violation from Insp on 980413-0508.Violations Noted:Two Examples Identified Where Licensee Not Performing Leakage Testing of safety-related Valves in Sys That Could Contain Highly Radioactive Fluids During Accident IR 05000245/19982081998-08-12012 August 1998 Insp Repts 50-245/98-208,50-336/98-208 & 50-423/98-208 on 980428-0629.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support ML20237B0741998-08-12012 August 1998 Notice of Violation from Insp on 980428-0629.Violation Noted:Licensee Failed to Direct Test Personnel to Close & Lock RHR Outboard Drain Valve IR 05000336/19982011998-08-12012 August 1998 Insp Rept 50-336/98-201 on 980413-0508.Violations Noted. Major Areas Inspected:Licensee Ability to Identify & Resolve Deficiencies Focusing,But Not Limited To,Period of CMP Implementation & ICAVP at Parsons Power Group,Inc PNO-I-98-026, on 980701,Millstone Unit 3 Criticality Update Made.Nrc Staff Continues to Provide Augmented Insp of Unit 3 Restart Activities,Including round-the-clock Coverage of Key Operational.Licensee Plans No Press Release1998-07-0101 July 1998 PNO-I-98-026:on 980701,Millstone Unit 3 Criticality Update Made.Nrc Staff Continues to Provide Augmented Insp of Unit 3 Restart Activities,Including round-the-clock Coverage of Key Operational.Licensee Plans No Press Release PNO-I-98-025, on 980630,unit 3 Established Reactor Criticality,However Reactor Was Shut Down When Control Room Operator Noticed Spiking Intermediate Range Monitor.Licensee Troubleshooting1998-06-30030 June 1998 PNO-I-98-025:on 980630,unit 3 Established Reactor Criticality,However Reactor Was Shut Down When Control Room Operator Noticed Spiking Intermediate Range Monitor.Licensee Troubleshooting IR 05000245/19982071998-06-19019 June 1998 Insp Repts 50-245/98-207,50-336/98-207 & 50-423/98-207 on 980301-0427.Violations Noted.Major Areas Inspected:Maint, Operations,Engineering & Plant Support ML20249C6931998-06-19019 June 1998 Notice of Violations from Combined Insp on 980301-0427. Violations Noted:Prior to 980424,instrument Min Accuracy of Wind Speed Channels Were Not Measured as Required by Table 3.3-8 of Unit 2 TS 3/4.3.3.4 IR 05000423/19970831998-06-12012 June 1998 Insp Rept 50-423/97-83 on 980413-24.Violations Noted. Major Areas Inspected:Readiness of Plant Hardware,Staff & Mgt Programs to Support Safe Restart & Continued Operation of Plant Unit 3 ML20249B0421998-06-12012 June 1998 Notice of Violations from Insp on 980413-24.Violations Noted:Only 1 RCS Loop Operable W/Plant in Mode 4 on 980407 IR 05000423/19970821998-06-11011 June 1998 Insp Rept 50-423/97-82 on 980209-20.Violations Noted.Major Areas Inspected:Corrective Actions Processes 1999-09-14
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U.S. NUCL. EAR REGULATORY COhih11SSION REGION I OPERATOR LICENSING REQUALIFICATION EXAMINATION REPORT REPORT N /92-25 (OL-RQ)
LICENSE N NPF-49 LICENSEE: Northeast Nuclear Energy Company ;
i FACILITY: Millstone Nuclear Power Station, Unit 3 DATES: November 16-19, 1992 3 CHIEF EXAMINER: -
44 /2 [h M
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Iiaul Bis'sett, Senior Op'erations Engineer Date PWR Section, Operations Branch, DRS EXAMINER:
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oaf 4 I2 1! b William Maier, Operations Engineer Date PWR Section, Operations Branch, D'RS J
APPROVED B haw 4 4 WM 12!A/#' d~- -
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nn W. Meyer, Chief, PWR Section - Dite perations Branch, DRS ,
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SUMMARY Requalification written examinations and operating tests were administered to l
two senior reactor operators (SROs) and two reactor operators (ROs)' These examinations were administered in accordance with proposed Revision;7 to NUREG-1021. T All four
operators passed their examinations. The two SROs and two RO3 also operated successfully -
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l as a crew during two simulator scenarios. The results from this examination were combined-with the results of the previous requalification examination administered in December 1991 in i- order to perform a program evaluation of the requalification training program. Seven SROs '
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and one RO were examined during the December 1991 examination, and all eight operators passed all portions of the examination. A program evaluation, however, had been deferred until completion of this year's examination, since a total of 12 licensed operators is needed for a program evaluatio ased upon the results of 12 licensed operators having been examined and successfully passing all portions of the examination, including the evaluation of 3 operating crews during the simulator evaluation, Millstone 3's licensed operator requalification training program was determined to be satisfactor In conjunction with this examination, the examiners inspected the programmatic aspects of the MP-3's licensed operator requalification training prograin. The purpose of this inspection was to ascertain whether there existed any generic deGeiencies that were common with those identified during the Millstone I unsatisfactory licensed operator requalification progra Upon completion of this inspection, it was determined that there were not any significant deficiencies similar to those identified with the Millstone I requalification training progra Some minor deficiencies, however, were identiGed, but were not considered to be significant enough to jeopardize the adequacy of the training progra . . . . _ _ .
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DETAllS TYPE OF EXAMINATION: Requalification EXAMINATION RESULTS:
RO Pass / Fail SRO Pass / Fail Total Pass / Fail Writtea 2/0 2/0 4/0 Simulator 2/0 2/0 4/0 Walk-through 2/0 2/0 4/0 Overall 2/0 2/0 4/0 The examination results noted above reflect 100% agreement between the NRC evaluators and the Millstone Plant-3 evaluator .0 PROGRAM EVALUATION RESUUTS: Itackground On October 15, 1992, representatives from the Millstone Plant, Unit 3 (MP-3) training department met in Region I with the NRC to discuss the scheduled November 1992 requalification examination. The purpose of the meeting was to discuss various aspects of the proposed Revision 7 to the Examiner Standards, under which the requalification examination would be conducted. The majority of discussion dealt with major differences between the approved Revision 6 and the proposed Revision 7 Further discussion dealt with administrative aspects of the examination. It was noted that results from the December 1991 requalification examination, in which c ght licenoed -
operators were examined, would be combined with the results of the upcoming November 1992 examination. A minimum of twelve licensed operators are needed in order for the NRC to make a training program evaluation. Four operators were scheduled for the November 1992 examination; and, when combined with the December 1991 examination, the minimum total of twelve operators examined would be met. Thus, a program evaluation could be performe From November 2 - 6,1992, the NRC reviewed the proposed examination with MP-3 training and operations representatives at the MP-3 site. This detailed review included a review of the adequacy of the written examination questions, a walkdown of all job performance measures (JPMs) and the validation of the ' simulator scenarios. The validation of the simtilator scenarios included a review of expected operator actions and the validity of '
designated crew critical task _ _ _ _ _ _ _ _ - _ _ - - _ _ __.__ . _ . . _ . . . _ _ _ _ _ _ _ _ _
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. Overall 1(ating: Satisfactory i
The hiillstone Plant, Unit 3 (h1P 3) program for licensed operator requalification training was !
rated satisfactory in accordance with the criteria established in the proposed Revision 7 of ES-601, "Administra:lon of NRC Requali0 cation Program Evaluation." Those criteria are r6 follows: At least 75% of all ogrators pan all portions of the examination. This number includes operators who participate in the simulator examination for the purpose of
- meeting crew composition requirement <
NRC grading is the only consideration for this criterion. There were no individuals who participated in the simulator portion of the examination in order to meet crew requirements. Twelve of twelve operators (100%) passed the examinatio ,
i 1 At least tu thirds (66%) of the crews pass the simulator examinatio ,
NRC grading is the o'ily consideration for this criterion. Three crews were evaluated, and all three crews (100%) passed the simulator portion of the operating examinatio l The requali0 cation program met these criteri .3 Progrmuniatic Strengths and Weaknesses i Strengths:
h1P-3 traming evaluators were very kno...edgeable in all aspects of the exam process and presented themselves in a very professional manner during the administration of the exam, i te training department also interfaced c)r" nely well with the operations departmen .
1 Weaknesses:
l Quality assurance reviews of examination material need to be strengthened prior to administration of the examination. Just prior to the administration of the written examination, it was determined that a couple of replacement questions had not been included in the SRO exam as requested by the examiner The exaniiners considered one proposed JPM to be too simple a task and was an inadequate tool to evaluate an operator's competency, Although the task was of importance and had a ~
high knowledge / abilities value, the JPhi itself did little from an evaluative standpoint. This particular JPhi was subsequently broadened in scope and depth, validated, and utilized during the examination.
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Scheduling of JPhi performance (time and location) warrants additional attention for future ;
examinations. Two operators had to wait an excessive amount o! time while awaiting the ;
start of their inplant JPhis. MP-3 training should be especially sensitive to this issue, since excessive delays add to undue operator stres ,0 REQUA1.1FICATION TRAINING PROGRAM INSPECTION t
As a result of the Millstone 1 unsatisfactory requalification training program evaluation and the fact that MP-1 and MP 3 operate from the same training facility and under the same organizational structure, it was determineo that an inspection of the MP-3 requalincation training program was warranted. The purpose of the inspection was to determine if any problems identified with the MP-1 requalincation training prograrn were also generic to the MP 3 training progra ,
During the conduct of this inspection, administrative reviews were performed, annuai MP-3 i
testing of licensed operators was observed, and discussions were held by the inspector vith both the training and operations personnel. During discussions with the operation .
department supervision, it was determined that they were taking an active role in assuring that their operators receive the training necessary to maintain a proficiency deemed necessary to ;
operate the plant in a safe manner. On a weekly basis, the operations manager, or his designee, participates with the training department in a simulator evaluation of the crew that just completed a week of requalification training. These evaluations are treated as if they were annual licensed operator requalincation examinations. Crew Performance that has been deemed less than acceptable requires that the crew or operator participate in an upgrade program designed to correct their identified areas 01 weaknesses, it was noted that management, both training and operations, up through the Director of Nuclear Training and Executive Vice President of Operations observe simulator training for MP 3 licensed operator .
As part of the MP-3's annual licensed operator requalification examinations, the inspector observed the performance of two simulator scenarios by one operating crew. Also observed was the debriefing conducted by the operations and training evaluators in regard to the crew's performance during the two scenarios. The evaluators stressed the area of communications as an identified area of weakness. The operations manager informed the inspector that he was in the process of developing a conduct of operations procedure that would address the area of communications, it was realized that there was no uniformity amongst crews or individuals when it came to communications. Because MP-3 has no formal communication standards, management has nothing to judge a crew's performance against and the operators havc no formalized communication goals to strive for. The operations manager expects that improvement in communications will be realized once the communication's standard is approved and applie _ _ _ _ _ ____-
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The inspector observed the performance of several JPMs and noted that they were performed and evaluated as if they were part of a NRC requalification examination. The MP 3 training !
department stated that they routinely schedule training on both the performance of any given l
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JPM and on the proper techniques of performing a JP The inspector performed a review of the MP 3's written examination bank. This review was l for the purpose of verifying the adequacy of examination questions in regard to level of difficulty, structure, content, etc. Approximately 40% of the existing bank questions were l selected for review. Of this 40%, approximately 60% of the questions were written as essay questions. The licensec stated that they are, and have been, reviewing the question bank and
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are either replacing the questions with newly written multiple choice questions or revising the existing essay questions to conform to the multiple choice question forma ,
The inspector also verified that MP-3 was conducting tt .r requalification program in accordance with the programmatic description as detailed in NTM 3.08, "LORT Program :
Implementing Procedure." For those areas reviewed, it appeared as if MP-3 training was, for the most part, implementing their training program as described, llowever, the procedure
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was not current in its description of how the grading was accomplished for the " A" & "11" sections of the written examinations. NTM 3.08 presently states that each section makes up :
one-Mif of the total written grade; but, with the changes that occurred as a result of Revision 7 to the Examiner Standards, this is no longer true. Grading of the two sections of the written examination should be based upon compensatory grading techniques. The training supervisor later informed the inspector that compensatory grading was utilized in the grading of the examinations; however, the procedure had not been revised to reflect thi Overall, it appears that MP 3 is adequately implementing their licensed operator requalification training program. As detailed above, certain areas warrant improvement, i.e.,
written examination question bank; however, no areas were identined as being inadequa;c to the point of having a detrimental effect on the training of MP 3's licensed operators. - EXIT MEETING On November 19,1992, at the conclusion T the requali0 cation examir ation, the NRC conducted an exit meeting at the Millstone training facility. Those personnel in attendance are noted in paragraph 6,0 of this report. Examination development and conduct, general observations noted during the exam, and programmatic strengths and weaknesses were
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discussed. Examination results, as determined by both the NRC and MP-3, were also discussed. Additionally, the conclusions reached by the examiner following his review of the implementation of the requalincation training program for MP-3 were presented, u
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7 KEY PEllSONNEl, CONTACTED:
Northeast Nuclear Energy Company
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- J. Illack Director, F m training
- C. Clement Director, M. 3
- !!. Parrish Assistant Supervisor, Operator Training M. Pearson Operations Manager, h1P-3
- 11. Ruth Manager, Operator Training
- C. Ryan Senior Operator - Instructor
- R. Stotts Training Supervisor, MP-3 U. S. Nuclear Regulatcry Commission
- P. Ilissett Senior Operations Engineer W. Maier Operations Engineer
- Denotes those present at the exit meeting conducted November 19, 199 _ _ - _ _ _ - - _ - _ - -