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Category:EXAMINATION REPORT
MONTHYEARML20154Q7381998-10-16016 October 1998 Second Suppl to NRC Exam Rept 50-354/98-03OL for Tests Administered on 980304-12,0519-21,22-28 & 0629.Five of Five Reactor Operator Applicants & Four of Five Senior Reactor Applicants Passed Exams IR 05000354/19980031998-10-16016 October 1998 Second Suppl to NRC Exam Rept 50-354/98-03OL for Tests Administered on 980304-12,0519-21,22-28 & 0629.Five of Five Reactor Operator Applicants & Four of Five Senior Reactor Applicants Passed Exams IR 05000354/19983011998-09-0404 September 1998 Exam Rept 50-354/98-301OL Conducted on 980810-12.Exam Results:Four SRO Candidates Performed Well on Both Written & Operating Portions of Exam.All Four Were Issued Licenses IR 05000354/19970081997-10-15015 October 1997 NRC Operator Licensing Exam Rept 50-354/97-08OL for Tests Administered on 970929-1002.Exam Results:Four Candidates Passed All Portions of License Exam.One Candidate Failed Written Exam ML20198L9531997-10-15015 October 1997 NRC Operator Licensing Exam Rept 50-354/97-08OL for Tests Administered on 970929-1002.Exam Results:Four Candidates Passed All Portions of License Exam.One Candidate Failed Written Exam IR 05000354/19930141993-07-0909 July 1993 Exam Rept 50-354/93-14OL on 930623-30.Exam Results:All Operators Passed Exam.One Unresolved Item Identified Re Plant Requalification Training Cycle Schedule IR 05000354/19900171990-11-0202 November 1990 Exam Rept 50-354/90-17OL on 900829,0924-28 & 1001-03.Exam Results:Eight RO & Nine SRO Candidates Passed IR 05000354/19900061990-05-16016 May 1990 Exam Rept 50-354/90-06OL on 900320-22.Exam Results:Two Out of Five Senior Reactor Operator Applicants Failed Exams & Licensee Submitted out-of-date Procedure IR 05000354/19890081989-09-22022 September 1989 Exam Rept 50-354/89-08OL on 890717-20.Exam Results:All Four Reactor Operator Applicants Passed IR 05000354/19890041989-04-0505 April 1989 Exam Rept 50-354/89-04OL on 890214-16.Exam Results:All Three Senior Reactor Operator Candidates Passed Written & Operating Exams.Housekeeping Problems Noted in Diesel Generator Rooms IR 05000354/19880121988-07-21021 July 1988 Exam Rept 50-354/88-12OL on 880411-15.Exam Results:Two Senior Operator Candidates & Three Reactor Operator Candidates Passed Exams & One Reactor Operator Candidate Failed Written Exam & Operating Test IR 05000354/19860341986-09-0808 September 1986 Exam Rept 50-354/86-34(OL) on 860707-11.Exam Results:All Candidates Passed Operating Exams.One Candidate Failed Written Exam IR 05000354/19860161986-04-30030 April 1986 Exam Rept 50-354/86-16 on 860224-28.Exam results:2 of 7 Reactor Operators & 2 of 11 Senior Reactor Operators Failed Written & Oral Exams & One Instructor Certification Candidate Passed IR 05000354/19850481986-02-0606 February 1986 Exam Rept 50-354/85-48 on 851014-23.Exam Results:All 13 Senior Reactor Operator Candidates Passed Oral Exam. One Candidate Failed Written & Simulator Exam.Two of 8 Reactor Operator Candidates Failed Written Exam ML20133K2831985-10-12012 October 1985 Exam Rept 50-354/OL-85-29 on 850708-17.Exam results:8 Reactor operators,11 Senior Reactor Operators & 1 Instructor Certification Candidate Passed Oral & Written Exams.Three Candidates Failed Simulator Exam 1998-09-04
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000354/19990051999-10-0101 October 1999 Insp Rept 50-354/99-05 on 990711-0829.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs.Major Areas Inspected:Mitigating Sys,Barrier Integrity & Performance Indicator Verification PNO-I-99-043, on 990916,Hurricane Floyd Was Approaching Ccnpp,Sgs,Hcgs & Ocnpp.Hurricane Was Centered at Latitude 36.0 North & Longitude 76.6 West & Moving north-northeast at Approx 25 Mph.Plants Remain at Power1999-09-16016 September 1999 PNO-I-99-043:on 990916,Hurricane Floyd Was Approaching Ccnpp,Sgs,Hcgs & Ocnpp.Hurricane Was Centered at Latitude 36.0 North & Longitude 76.6 West & Moving north-northeast at Approx 25 Mph.Plants Remain at Power IR 05000354/19990041999-08-11011 August 1999 Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted. Major Areas inspected:cornerstone-mitigating Sys,Pi Verification IR 05000354/19990031999-06-21021 June 1999 Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19990021999-05-14014 May 1999 Insp Rept 50-354/99-02 on 990308-0418.Non-cited Violation Identified.Major Areas Inspected:Operations,Maint & Plant Support IR 05000354/19990011999-04-19019 April 1999 Insp Rept 50-354/99-01 on 990124-0307.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000354/19980111998-12-22022 December 1998 Insp Rept 50-354/98-11 on 981101-1212.No Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000354/19980101998-11-23023 November 1998 Insp Rept 50-354/98-10 on 980920-1031.Violations Noted. Major Areas Inspected:Operations,Maint & Engineering ML20196D0911998-11-23023 November 1998 Notice of Violation from Insp on 980920-1031.Violation Noted:On 981001,electricians Placed Single Degraded Cell Associated with Operable 1E Battery Bank on Single Cell Charge PNO-I-98-053, on 981115,plant Experienced Turbine Trip While Operating at 95% Power Due to High Level Condition on One of Two Moisture Separators.Reactor Automatically Shut Down.Util Evaluating Incorrect Sys Drawing.States of Nj & DE Notifie1998-11-16016 November 1998 PNO-I-98-053:on 981115,plant Experienced Turbine Trip While Operating at 95% Power Due to High Level Condition on One of Two Moisture Separators.Reactor Automatically Shut Down.Util Evaluating Incorrect Sys Drawing.States of Nj & DE Notifie ML20154Q7381998-10-16016 October 1998 Second Suppl to NRC Exam Rept 50-354/98-03OL for Tests Administered on 980304-12,0519-21,22-28 & 0629.Five of Five Reactor Operator Applicants & Four of Five Senior Reactor Applicants Passed Exams IR 05000354/19980031998-10-16016 October 1998 Second Suppl to NRC Exam Rept 50-354/98-03OL for Tests Administered on 980304-12,0519-21,22-28 & 0629.Five of Five Reactor Operator Applicants & Four of Five Senior Reactor Applicants Passed Exams IR 05000354/19980081998-10-0909 October 1998 Insp Rept 50-354/98-08 on 980809-1019.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20154J8611998-10-0909 October 1998 Notice of Violation from Insp on 980809-0919.Violation Noted:On 980831,licensee Did Not Promptly Correct Condition Adverse to Quality in That C Residual Heat Removal Pump Rendered Inoperable IR 05000354/19980091998-10-0202 October 1998 Insp Rept 50-354/98-09 on 980817-26 & 0908.No Violations Noted.Major Areas Inspected:Maint & Engineering IR 05000354/19983011998-09-0404 September 1998 Exam Rept 50-354/98-301OL Conducted on 980810-12.Exam Results:Four SRO Candidates Performed Well on Both Written & Operating Portions of Exam.All Four Were Issued Licenses IR 05000354/19980071998-08-25025 August 1998 Insp Rept 50-354/98-07 on 980628-0808.Violation Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20237E4981998-08-25025 August 1998 Notice of Violation from Insp on 980628-0808.Violation Noted:As of 980810,util Had Not Corrected Known Deficiency in Verifying MSIV Full Closed During Springs Only Full Stroke Closing Tests ML20236T1601998-07-21021 July 1998 Notice of Violation from Insp on 980517-0627.Violation Noted:As of Oct 1997,chemistry Technicians Did Not Sample & Analyze Diesel Fuel Oil Deliveries for Particulates & Did Not Report Results by Written Notification within 14 Days IR 05000272/19982021998-07-0909 July 1998 Partially Deleted Insp Repts 50-272/98-202,50-311/98-202 & 50-354/98-202 on 980420-23.No Violations Noted.Major Areas Inspected:Conduct of Security & Safeguards Activities IR 05000354/19980801998-06-10010 June 1998 Insp Rept 50-354/98-80 on 980223-0319 & 0427-30.Violations Noted.Major Areas Inspected:Maint & Engineering ML20249A2031998-06-10010 June 1998 Notice of Violation from Insp on 980223-0319 & 0427-30. Violation Noted:Conditions Adverse to Quality Were Not Promptly Identified & Corrected IR 05000354/19980991998-06-0808 June 1998 SALP Rept 50-354/98-99 for Period of 961110-980516 ML20249A1071998-06-0404 June 1998 Notice of Violation from Insp on 980405-0516.Violation Noted:During Refueling Outage RF03 in Dec 1990 Licensee Did Not Maintain RHR Sys in Operation ML20217N6221998-04-24024 April 1998 Notice of Violation from Investigation Conducted by Oi. Violation Noted:Safeguard Event Log,Required to Be Maintained by Licensee,Was Not Complete & Accurate in All Matl Aspects ML20217H8051998-04-23023 April 1998 Notice of Violation from Insp on 980222-0404.Violation Noted:Three Examples of Inadequate Accomplishment of Procedure Control Associated W/Temporary Equipment Installed in Plant Svc Water Intake Structure ML20217C6711998-03-20020 March 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:On 971112,while Reactor Was in Cold Shutdown W/Rv Head Removed,Operators Did Not Verify That CR Position Did Not Change During Withdrawal ML20217D8291998-03-17017 March 1998 EN-98-013:informs That NOV & Proposed Imposition of Civil Penalty in Amount of $55,000 Will Be Issued on or About 980330 to Pse&G.Civil Penalty Based on Violation Involving Failure by Operating Crew to Follow Procedures IR 05000354/19980011998-03-16016 March 1998 Insp Rept 50-354/98-01 on 980104-0221.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000354/19970101998-02-0303 February 1998 Insp Rept 50-354/97-10 on 971116-980103.Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20199L4791998-02-0303 February 1998 Notice of Violation from Insp on 971126-980103.Violation Noted:On 971124,maint Technicians Failed to Follow HC.IC-DC.ZZ-0140(Q),Rev 3, Device/Equipment Calibration Masonleilan Pressure & Temperature Controllers IR 05000354/19970091997-12-10010 December 1997 Insp Rept 50-354/97-09 on 971005-1115.Apparent Violation Being Considered for Escalated Ea.Major Areas Inspected: Licensee Operations,Engineering,Maint,Plant Support & Site Security Programs ML20199D3431997-11-13013 November 1997 Insp Rept 50-354/97-07 on 970824-1004.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support IR 05000354/19970071997-11-13013 November 1997 Insp Rept 50-354/97-07 on 970824-1004.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support ML20199D3171997-11-12012 November 1997 Notice of Violation from Insp on 970824-1004.Violation Noted:On 970914,electric motor-driven Fire Pump Supply Breaker Opened During Electrical Bus Swap Which Rendered Pump Inoperable ML20196J6531997-10-20020 October 1997 Notice of Violation from Insp on 970202 & 0317.Violation Noted:In Apr 1994,licensee Made Changes to Facility That Involved USQ Without Prior Commission Approval IR 05000354/19970081997-10-15015 October 1997 NRC Operator Licensing Exam Rept 50-354/97-08OL for Tests Administered on 970929-1002.Exam Results:Four Candidates Passed All Portions of License Exam.One Candidate Failed Written Exam ML20198L9531997-10-15015 October 1997 NRC Operator Licensing Exam Rept 50-354/97-08OL for Tests Administered on 970929-1002.Exam Results:Four Candidates Passed All Portions of License Exam.One Candidate Failed Written Exam IR 05000354/19970051997-09-15015 September 1997 Insp Rept 50-354/97-05 on 970713-0823.Noncited Violations Identified.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000354/19970061997-09-0404 September 1997 Insp Rept 50-354/97-06 on 961112-970529.Violations Noted. Major Areas Inspected:Engineering IR 05000354/19970041997-08-11011 August 1997 Insp Rept 50-354/97-04 on 970601-0712.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20210N9061997-08-11011 August 1997 Notice of Violation from Insp on 970601-0712.Violation Noted:Inoperable HPCI Sys Injection Valve Was Not Promptly Identified ML20217E7851997-07-25025 July 1997 Investigation Rept 1-96-024 on 970725.No Noncompliance Noted.Major Areas Investigated:Allegations Re Failure to Make 10CFR73.71 Notification by Station Security Dept ML20140J3811997-06-12012 June 1997 Notice of Violation from Insp on 970429-0531.Violation Noted:Failing to Adhere to Established Procedural Guidance for safety-related Activities Were Identified,Significant Condition Adverse to Quality IR 05000354/19970031997-06-12012 June 1997 Insp Rept 50-354/97-03 on 970429-0531.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20148D2011997-05-23023 May 1997 Notice of Violation from Insp on 970318-0428.Violation Noted:On 970423,operators Failed to Shut Six of Twelve Cylinder Indicator Test Cocks Following Completion of C Emergency Diesel Generator pre-start Checks ML20148D2301997-05-23023 May 1997 Insp Rept 50-354/97-02 on 970318-0428.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support.Routine Insp of Physical Protection & Security Program Also Conducted IR 05000354/19970021997-05-23023 May 1997 Insp Rept 50-354/97-02 on 970318-0428.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support.Routine Insp of Physical Protection & Security Program Also Conducted ML20137W7701997-04-14014 April 1997 Notice of Violation,App a for Insp on 970202-0317.Violation Noted:On 970226,scaffolds Installed in safety-related Areas, Including a & B RHR Pump Rooms & Standby Liquid Control Pump Room in Rb,Lacked Appropriate Construction Documentation ML20137W7811997-04-14014 April 1997 Insp Rept 50-354/97-01 on 970202-0317.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint, & Plant Support 1999-09-16
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U. S. NUCLEAR REGULATORY COMMISSION
REGION I
Docket No.
50-354 Report No.
50-354/93-14 (OL)
License No.
NPF-57 Licensee:
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Facility:
Hope Creek Nuclear Generating Station Dates:
June 23,1993 and June 30,1993 Examiners:
D. Florek, Senior Operations Engineer C. Sisco, Operations Engineer N
Chief Examiner:
D."Florek,' Senior Operations Engineer, BWR Date
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Section, Operations Branch
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Approved By:
If Con (e 'hief BWR Section, Operations bate Brancl/
ivision of Reactor Safety Examination Summary: Examination conducted June 23 and 30.1993 (Insoection Reoort 50-354/93-14 (OLD
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Requalification examinations were administered to two senior reactor operators and two reactor operators on one crew. All operators passed the examination. The operators were well prepared for the examination. The e. amination identified a weaknesses in the procedure
for shifting control rod drive flow control valves. One unresolved item was identified related to the Hope Creek requalification training cycle schedule.
9307270024 930720 PDR ADOCK 05000354 PDR'
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DETAILS
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i 1.0 INTRODUCTION
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On June 23 and June 30,1993, the NRC administered requalification examinations to two
senior reactor operators and two reactor operators. The examiners used the process and
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criteria described in NUREG 1021, " Operator Licensing Examiner Standard," Rev. 7.
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An exit meeting was conducted on June 30,1993. Those present at the exit are listed in i
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2.0 EXAMINATION RESULTS
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2.1 NRC Requalification Retake Examination Results
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RO SRO TOTAL.
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Pass / Fail Pass / Fail
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Written 2/0 2/0 4/0 i
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Simulator 2/0 2/0 4/0
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Walk-through 2/0 2/0 4/0-
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Overall 2/0 2/0 4/0
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The crew also passed in the simulator.
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2.2 Facility Licensee Requalification Retake Examination Results
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RO SRO
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.j Pass / Fail Pass / Fail Pass / Fail
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Written.
2/0 2/0 4/0
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Simulator 2/0 2/0 4/0
Walk-through 2/0 2/0 4/0 i
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i The crew also passed in the simulator.
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2.3 Facility Generic Strengths and Weaknesses Based on Individual Operator
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Performance on Examinations
The step in job performance measure (JPM) 305H-JPM.BF-001-03, " Shift In-Service CRD.
Flow Control Valves," to " adjust increase knob on valve B(A) until both controllers indicate
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the same position" was incorrectly performed by three of the four operators that resulted in
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the three operators failing the JPM. The examination identified that a weakness in the
.1 procedure led to the operator response.
i During one of the simulator scenarios, the senior operator was questioned on the emergency i
operating procedure (EOP) direction for use of high pressure coolant injection (HPCI) during an anticipated transient without scram (ATWS) condition. The operator indicated that HPCI could not be used during an ATWS unless the HPCI line to the core shroud area was
isolated. The Operations Manager indicated that the operator's answer was not consistent
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with the Hope Creek analysis that indicated that HPCI could be used without the core shroud
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area injection line isolated if HPCI was needed to maintain RPV water level above top of active fuel. The Operations Manager has noted that other crews were also having some
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confusion on the EOP procedure direction use of HPCI during an ATWS and was pursuing possible procedure changes in this area.
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. The operators were well prepared for the examinations. Strong teamwork and good
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communication were evident during the requalification examination simulator scenarios.
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3.0 PROGRAM EVALUATION Because of the limited number of licensed operators examined a program evaluation could not be performed. In accordance with the examiner standards, the NRC staff will defer its program evaluation until NRC staff administers requalification examinations to at least 8 additional licensed operators. However, in inspection report 50-354/93-13 the NRC staff assessed portions of the Hope Creek requalification training program. Notwithstanding the limitations on examination sample size for a program evaluation, the inspection and
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examination results indicate that the Hope Creek requalification program would remain a satisfactory program.
4.0 EXAMINATION DEVELOPMENT
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During the preparation phase of the examination, the examination team made some modifications to the facility licensee proposed examination. For the walkthrough portion of the examination, the examination team created a new JPM to locally adjust recirculation pump speeds and revised some JPM standards to be objective. For the written portion of the examination the examination team revised the written examination and substituted questions and moved the systems type questions to the static portion and the procedure use questions to
the classroom portion as described in the examiner standards. As a result of this adjustment to the written examination, the facility licensee classroom written examination bank was noted to be weak in the number of written questions in the emergency planning area. For the simulator portion of the examination the scenario contents were acceptable; however, the standards were revised to be objective in nature. The facility licensee was cooperative in making the adjustments to the examination.
During the validation of the JPM to implement emergency operating procedure HC.OP-EO.ZZ-0321, it was noted that the procedure did not accurately account for electrical tape needed to lift and tape the identified leads. The local emergency operating procedure tool kit did, however, contain the needed tape. The facility licensee representative indicated that they will revise the procedure.
5.0 IIOPE CREEK REQUALIFICATION TRAINING CYCLE The examiner reviewed and discussed the Hope Creek requalification training cycle schedule with the Hope Creek Principal Training Supervisor and reviewed SH.TO-TC.ZZ-0305,
"NRC Licensed Operator Requalification Program," dated June 9,1993. A licensed
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operator at Hope Creek will get four-two week requalification training segments over the
I year, with the first segment normally starting in September. Due to the five shift rotation which includes staff licenses, each segment runs 10 weeks. When the segment is completed, another segment immediately starts until the four segments are completed. The end of the fourth segment contains the required examination. For 40 weeks per year (September to June) licensed operators receive formal training and for 12 weeks per year (June to September) no scheduled requalification training is performed. For this year, the fourth
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5 operators receive formal training and for 12 weeks per year (June to September) no scheduled requalification training is performed. For this year, the fourth requalification segment ended oa June 17,1993, and the first segment will start on September 14, 1993.
There are two potential problems with the facility schedule. The first is the length of time between training segments four and one may result in degradation of operator proficiency.
Due to the shift rotation, one crew of operators will go 28 weeks between the end of training segment four and the beginning of training segment one. The four other crews will go 18 weeks between training segment four and training segment one. The operator proficiency in the dynamic response in the simulator and keeping abreast of procedure and plant modifications has the potential to be degraded. The second is whether the facility schedule -
meets the requirements of 10 CFR 55.59(c)(1) " conducted for a continuous period not.*o exceed two years, and upon conclusion must be promptly followed, pursuant to a continuous schedule, by successive requalification programs." Since one of the segment 4's is the end of the training for the two year cycle, the 12 weeks before the start of segment 1 may not meet the intent of a "promptly followed" or " continuous period" part of the regulations. The facility licensee representative indicated that the NRC staff had reviewed and accepted the Hope Creek training schedule as part of the initial licensing process. Pending additional _
review by the NRC staff, this item is unresolved. (354/93-14-01)
6.0 PERSONS CONTACTED Public Service Electric and Gas
- W. Gott, Principal Trainer Hope Creek
- G. Mecchi, Principal Trainer Operations Training
- W. O'Malley, Hope Creek Operations Manager
- A. Orticelle, Manager Operations Training Nuclear Regulatory Commission
- D. Florek, Sr. Operations Manager
- C. Sisco, Operations Engineer
- Denotes those present at the exit meeting on June 30,1993.
7.0 EXIT MEETING An exit meeting was conducted on June 30,1993. Personnel in attendance are listed in Secdon 6.0. The facility licensee presented their examination results at the exit that indicated that all operators and the crew passed the examination. The NRC presented the examination related findings. The facility representatives acknowledged the NRC finding....
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ATTACIIMENT 1 SIMULATION FACILITY REPORT Facility Licensee: Public Service Electric and Gas Company Facility Docket: 50-354 Operating Tests Administered on: June 30,1993 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 observations.
While conducting the simulator portion of the operating tests, the following items were observed:
ITEM DESCRIPTION 1.
Simulator interface with the Control Room Integrated Display (CRID) computer was not operational that resulted in rescheduling of the dynamic simulator operating test and static simulator written test from the week of June 21 to June 28,1993. A cable failure was identified as the cause and successfully repaired.
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