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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. NUCLEAR REGULATORY COMMISSION REGION 1 OPERATOR LICENSING REQUAl.lFICATION EXAMINATION REPORT REPORT NO.: 50-336/92-33 (OL-RQ)
LICENSE NO.: DRP-65 LICENSEE: Northeast Nuclear Energy Company P. O. Box 270 Hartford, CT 06141-0270 FACILITY: Millstone Nucicar Power Station, Unit 2 DATES: December 14 - 17, 1992 EXAMINER: Mark Jones, NRC Consultant (EG&G)
D CHIEF EXAMINER: M 27 h5 Kerry D. Ihnen, Operations Engineer Date PWR Section, Operations Branch, DRS APPROVED BY: /R ~M ft/ b Glenn M Meyer, C'hief, PM Section
/ 7 95 Dite /
Operations Branch, DRS SUMMARY: Requalification written examinations and operating tests were administered to three senior reactor operators (SROs) and two reactor operators (ROs). These examinations were administered in accordance with proposed Revision 7 to NUREG 1021. The quality of the written exams was improved as compared to previous written exams. All five operators passed their examinations. The three SROs and two ROs also operated successfully as a crew during two simulator scenarios. The results from this examination were combined with the results of the previous requalification examination administered in April 1992 in order to perform a program evaluation of the requalification training program. Six SROs and three ROs were examined during the April 1992 examination, and all nine operators passed all portions of the examination. A program evaluation, however, had been deferred until completion of this examination, since a total of 12 licensed operators is needed for a program evaluation.
Based upon the results of 14 licensed operators having been examined and successfully passing all portions of the examination including the evaluation of 3 operating crews during the simulator evaluatien, Millstone 2's licensed operator requalification training program was
/ determined to be satisfactory, gRo2100351 93012e y ADOCK 05000336 PDR s
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In conjunction with this examination, the examher inspected the programmatic aspects of the Mp-2's licensed operator requal10 cation training program. The purpose of this inspection was to ascertain whether there existed any generic denciencies that were common with those identined during the Millstone 1 unsatisfactory licensed operator requalincation program.
Upon completion of this inspection, it was determined that there were no significant denciencies similar to those identl0cd with the Millstone 1 requall6catien training program.
1 mM =?,
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e DETAllE TYPE OF EXAMINATION: Requalification 1.0 EXAMINATION RESULTS:
BI RO Pass / Fail SRO Pass / Fail Total Pass / Fail Written 2/0 3/0 5/0 Simulator 2/0 3/0 5/0 Walk-through 2/0 3/0 5/0 Overall 2/0 3/0 5/0 The examination results noted above reflect 100% agreement between the NRC evaluators and the Millstone Unit 2 evaluators.
2.0 PROGRAM EVALUATION RESULTS 2.1 Background On November 4,1992, representati.e. from the Millstone Plant, Unit 2 (MP-2) training department met in Region I with the NRC to discuss the scheduled December 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 c 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 April 1992 requalification examination, in which nine licensed operators were examined, would be combined with the results of the upcoming December 1992 examination. A minimum of twelve licensed operators are needed in order for the NRC to make a training program evaluation. Five operators were scheduled for the December 1992 examination and when combined with the April 1992 examination, the minimum total of twelve operators examined would be met. Thus, a program evaluation could be performed.
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From December 1 - 4, 1992, the NRC reviewed the proposed examination with MP-2 training and operations representatives at the MP-2 site. This detailed review included a r >iew of the adequacy of the written examination questions, a walkdown of alljob
- erformance measures (JPMs) and the validation of the simulator scenarios. The validation of the simulator scenarios included a review of expected operator actions and the validity of designated crew ctitical tasks.
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2.2 Overall Rating: Satisfactory The Millstone Plant, Unit 2 (MP-2) program for licensed operator requalification training was rated satisfactory in accordance with the criteria established in the proposed Revision 7 of ES-601, " Administration of NRC Requalification Program E Nuation." Those criteria are as follows:
A. At least 75% of all operators pass all portions of the examination. This number includes operators who participate in the simulator examination for the purpose of meeting crew composition requirements.
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. Fourteen of fourteen operators (100%) passed the examination.
B. At least two-thirds (66%) of the crews pass the simulator examination.
NRC grading is the only consideration for this criterion. Three crews were evaluated, and all three crews (100%) passed the simulator portion of the operating examination.
The requalification program met these criteria and was rated as satisfactory.
2.3 Programmatic Strengths and Weaknesses
'
A. Strengths:
- '4 e MP-2 training evaluators were very knowledgeable in all aspects of the exam l
process and presented themselves in a very professional manner during the
- administration of the exam.
I i e The written and simulator exams were improved and were good tools in
- determining the competencies of the operators.
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e The crew examined on the simulator demonstrated good teamwork and effective face-to-face communications.
B. Weaknesses:
!
l No weaknesses were noted.
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3.0 REQUALIFICATION TRAINING PROGRAM INSPECTION h
As a result of the Millstone 1 unsatisfactory requalification training program evaluation and
- the fact that MP-1 and MP-2 operate from the same training facility and under the same organizational structure, it was determined that an inspection of the MP-2 requalification training program was warranted. The purpose of the inspection was to determine if any
'
problems identified with the MP-1 requalification training program were also generic to the
MP-2 training program.
I
- In conjunction with this examination, the examiner inspected the programmatic aspects of the
- MP-2's licensed operator requalification training program. The purpose of this inspection
- was to ascertain whether there existed any generic deficiencies that were common with those
' identified during the Millstone 1 unsatisfactory licensed operator requalification program.
] Upon completion of this inspection, it was determined that there were no significant deficiencies similar to those identified with the Millstone I requalification training program.
j 4.0 EXIT MEETING On December 17,1992, at the conclusion of the requalification examination, the NRC
- conducted an exit meeting at the Millstone training facility. Those personnel in attendance are noted in paragraph 4.0 of this report. Examination development and conduct, general l
observations noted during the exam, and programmatic strengths and weaknesses were
"
discussed. Examination results, as determined by both the NRC and MP-2, were also discussed.
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5.0 KEY PERSONNEL CONTACTED:
- Northeast Nuclear Energy Company
- B. P.uth Manager, Operator Training '
- J. Smith Operations Manager, MS-2
! * R. Spurr Training Supervisor, MP-3 i
[ U. S. Nuclear Regulatory Commission
- K. Ihnen Operations Engineer
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M. Jones NRC Consultant j * R. Laufer NRR/OLB
- Denotes those present at the exit meeting conducted December 17, 1992.
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ATTACHMENT 1
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NORTHEAST UTILITIES mm , w cenere omce. . seiden street. Bernn. connect. cut
., sm. ww-l .m ms m u m w~
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P.O. BOX 270 H ARTFORD. CONNECTICUT 06141-0270 k k J 2 [.- [ M 7 [ '[ (203) 665-5000 January 11, 1993 MP-93-36 RE: NUREG 1021, ES-601 Mr. Lee Chief, Operations Branch, DRS U. S. Nuclear Regulatory Commission, Region 1 475 Allendale Road King of Prussia, PA 19406 REFERENCE: Facility Operating License No. DPR-65 Docket No. 50-336 NRC Requalification Examination Summary
Dear Mr. Bettenhausen:
During the week of December 14, 1992, Licensed Operator Requalification Examinations were administered to five Millstone Unit 2 Licensed Operators and Senior Licensed Operators. These examinations w6re conducted in accordance with tho applicable sections of the Revision 7 draft of NUREG 1021, Operator Licensing Examiner Standards. Accordingly, the examinations were prepared, administered, and evaluated by both NRC and facility examiners.
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Preliminary results of the facility evaluations for all portions of the examination were provided to Mr. Kerry Ihnen, NRC Chief Examiner, en December 16, 1992. Based on our review of the exam grading, these results can be considered final. Attached is a summary of our grades.
An evaluation of the examination results was performed to identify strengths and weaknesses, both individual and crew, and to identify necessary remediation and enhancements to the MP2 Licensed Operator Requalification Program content. The following is a summary, by examination environment, of the evaluation:
SIMULATOR EXAMINATIONS STRENGTHS:
o Teamwork, communications and crew interaction. Where appropriate, team members were involved in decision-making and shared with each other information concerning event strategy and inter-watchstation operations. Individual team members operated within their pre-detined roles.
Communications was especially strong.
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o Proper selection and implementation of emergency operating
- procedures.
s j o Attention to annunciators and use of the alarm response procedures.
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o Diagnosis of events, both major and minor.
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o Event classification in accordance with the emergency plan i WEAKNESSES:
i i- None of- the weaknesses listed below .are considered of such
- significance that they require formal individual orf crew
- remediation. Where appropriate, increased emphasis will be placed
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on these items during simulator training sessions..
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o One RO attempted to . throttle auxiliary feed regulating j valves with the controller in Auto. The operator realized.
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his oversight, shifted the controllers to manual and then
throttled the valves.
) o In one scenario the PPO restored letdown flow without
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{ adequately checking the availability of Reactor Building j- Closed Cooling Water (RBCCW). The B RBCCW header, which supplies letdown heat exchanger cooling, was initially unavailable due to a-loss-of facilityi2-emergency power.
i. The SPO was restoring . facility 2 power .and vital
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auxiliaries in parallel with the PPO's reinitiation of
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letdown. RBCCW was independently restored prior to any system feedback to the PPO.
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j . WALKTHROUGH EXAMINATION
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- The examinees demonstrated a high degree of proficiency and
knowledge -for the tasks examined. All JPM's were performed
satisfactorily.
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WRITTEN EXAMINATION i Examinee performance on the written examination was generally
excellent, showing a sound mastery of the learning objectives examined. There were no weaknesses identified.
Yours Truly, NORTHEAST NUCLEAR ENERGY COMPANY A
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< Stephe E. Scace
- Station Vice President Millstone Nuclear Power Station
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Attachment SES/RNS/dsb
! Document Control Desk, US NRC c:
B. W. Ruth, Manager, Operator Training i
R. M. Kacich, Director, Nuclear Licensing, NU
. K. Ihnen, US NRC
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W. J. Raymond, NRC Resident Inspector
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LORT EXAMINATION SUMMARY WEEK OF DECEMBER 14,1992 l
SS 1 OPEN WRITTEN SINULATOR REFERENCE TOTAL JPM'S NAME FAC. NRC FAC. NRC FAC. NRC 22/23 97.82 Sat OPERATOR A Sat 13/13 100% 95.65 I
Sat .13/13 23/23 100 Sat OPERATOR B 100% 100 Sat .13/13 22/23 97.82 Sat OPERATOR C'
100% 95.65 OPERATOR D Sat- 12.75/13 22/23 96.82 Sat 98% 95.65 l
OPERATOR'E Sat 12.75/13 20/23 92.48 Sat 98% 86.96 l
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o o 1 A'ITACIIMFNr 2 SIMULATION FACILITY REPORT l Facility Licensee: MP-2 Facility Docket No.: 50-336 Requalification Examinations Administered from: December 15 - 17, 1992 This fonn is used only to report observations. These observations do not constitute audit or inspection findings and are not, without further verification and review, indicative of non-compliance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations. No licensee action is required in response to these observations.
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During the conduct of the simulator portion of the operating tests, the following item was observed.
ITEM DESCRIPTION Subcooled Margin and Natural circulation flo v when at saturated conditions is not pressurizer level accurately modeled by the single phase reactor coolant system (RCS) model. As the
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core temperature increased to saturation, the model causes a large steam void in the upper vessel region and an associated increase in pressurizer level. This is shown as a loss of subcooled margin. The step increase in pressurizer level causes a step increase in RCS pressure. The step increase in RCS pressure seen in the next iteration causes the vessel to be significantly subcooled and the steam void disappears. ' Mass is transferred from the pressurizer to the vessel causing a step decrease in pressurizer level. This step decrease in pressurizer level causes a step decrease in RCS pressure. Saturation conditions exist again in the vessel and the steam void reappears, starting the cycle all over again. This cycle would continue to repeat on approximately 30 second intervals.
Northeast Utilities is currently working with the vendor to acquire new two-phase codes for the RCS.