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Category:EXAMINATION REPORT
MONTHYEARML20217C6691991-07-0808 July 1991 Exam Rept 50-297/OL-91-01 on 910603-04.Exam Results:Both Applicants Passed Exam ML20154D2561988-05-0505 May 1988 Exam Rept 50-297/OL-88-02 on 880426.Exam Results:Reactor Operator Passed ML20150B2371988-02-23023 February 1988 Exam Rept 50-297/OL-88-01 on 880202-03.Exam Results:One of Two Reactor Operators Passed Written Exam & Operating Exam & Senior Reactor Operator Passed Both Exams ML20211A4381986-05-19019 May 1986 Exam Rept 50-297/OL-86-01 on 860423-24.Exam Results:All Five Candidates Passed Oral & Written Exams 1991-07-08
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000297/19992011999-03-0202 March 1999 Insp Rept 50-297/99-201 on 990209-12.No Violations Noted. Major Areas Inspected:Routine,Announced Insp Included Onsite Review of Various Aspects of Licensee Programs Concerning Conduct of Operations & Emergency Preparedness ML20217C0501998-03-18018 March 1998 Notice of Violation from Insp on 980120-23.Violation Noted: Licensee Developed Various Health Physics Instructions That Were Reviewed & Approved by Reactor Health Physicist,But Not by Radiation Protection Committee ML20217C0721998-03-18018 March 1998 Insp Rept 50-297/98-201 on 980120-23.Violations Noted.Major Areas inspected:on-site Review of Selected Aspects of Licensee Class II Nonpower Research Reactor Operation Including;Safeguards,Security Program & Matl Control IR 05000297/19972011997-09-0909 September 1997 Insp Rept 50-297/97-201 on 970609-12.No Violations Noted. Major Areas Inspected:Review of Selected Conditions & Records Since Last Insp & Verification of CA Previously Committed to by Licensee IR 05000297/19930021993-10-15015 October 1993 Partially Withheld Insp Rept 50-297/93-02 on 930928-29 (Ref 10CFR2.790).No Violations Noted.Major Areas Inspected: Procedures,Fixed Site Physical Protection of Special Nuclear Matl of Low Strategic Significance & Matl Control ML20217C6691991-07-0808 July 1991 Exam Rept 50-297/OL-91-01 on 910603-04.Exam Results:Both Applicants Passed Exam IR 05000297/19900021990-11-14014 November 1990 Insp Rept 50-297/90-02 on 901029-1101.No Violations or Deviations Noted.Major Areas Inspected:Review & Oversight of Reactor Activities IR 05000297/19890031989-09-28028 September 1989 Partially Withheld Insp Rept 50-297/89-03 on 890907 (Ref 10CFR2.790).No Violations or Deviations Noted.Major Areas Inspected:Nuclear Matl Accounting Records & Repts & Physical Inventory IR 05000297/19890021989-09-15015 September 1989 Partially Withheld Insp Rept 50-297/89-02 on 890817 (Ref 10CFR2.790).No Noncompliance Noted.Major Areas Inspected: Plans & Procedures,Repts of Safeguards Events & Fixed Site Physical Protection of SNM of Low Strategic Significance ML20245G2321989-08-0202 August 1989 Notice of Violation from Insp on 890628-30.Violations Noted: Failure to Provide Adequate Training to Radiation Safety Ofc Personnel Performing Contamination Surveys & Failure to Follow Environ Procedures for Collecting Air Filters ML20245G2371989-08-0101 August 1989 Insp Rept 50-297/89-01 on 890628-30.Violation Noted Major Areas Inspected:Staff Organization,Training,Radiation Control & Surveillance Activities,Environ Monitoring & Transportation Activities ML20205R0001988-11-0202 November 1988 Notice of Violation from Insp on 880926-29.Violation Noted: Failure to Have & Maintain Approved Procedures Utilized by Radiation Protection Ofc to Conduct Liquid Effluent & Environ Sample Radiological Analyses IR 05000297/19880041988-10-31031 October 1988 Insp Rept 50-297/88-04 on 880926-29.Violations Noted.Major Areas Inspected:Onsite Review of Licensee Radiation Protection Program,Including Staff Organization,Training, Radiation Control & Surveillance Activities ML20195J3641988-06-13013 June 1988 Notice of Violation from Insp on 880523-26.Violation Noted: Reactor Safeguards Advisory Group Did Not Meet During 870408-880225 IR 05000297/19880031988-06-0909 June 1988 Insp Rept 50-297/88-03 on 880523-26.Violation Noted.Major Areas Inspected:Recent Activities to Reduce & Monitor Pool Leakage & Completed Biennial Insp of Licensee ML20154D2561988-05-0505 May 1988 Exam Rept 50-297/OL-88-02 on 880426.Exam Results:Reactor Operator Passed IR 05000297/19880011988-04-0404 April 1988 Insp Rept 50-297/88-01 on 880301-04.No Violations or Deviations Noted.Major Areas Inspected:Leaks in RCS Piping Outside Reactor Bldg & in Isolable Portion of Reactor Primary Sys within Bldg PNO-II-88-015B, on 880229,licensee Informed NRC That 1 Mwt Pool Reactor Had Been Shutdown Due to Primary Coolant Leak Outside Containment.Two Leaks Identified.Util Plans to Isolate Leak & Test Further to Assure That Leak Is in Liner1988-03-24024 March 1988 PNO-II-88-015B:on 880229,licensee Informed NRC That 1 Mwt Pool Reactor Had Been Shutdown Due to Primary Coolant Leak Outside Containment.Two Leaks Identified.Util Plans to Isolate Leak & Test Further to Assure That Leak Is in Liner PNO-II-88-015A, analysis of Reactor Water Sample Indicates That Concentrations of Radionuclides Less than NRC Limit for Release to Unrestricted Area.Cold Leg Has Been Drained & Leg Currently Being Drained1988-03-0303 March 1988 PNO-II-88-015A:analysis of Reactor Water Sample Indicates That Concentrations of Radionuclides Less than NRC Limit for Release to Unrestricted Area.Cold Leg Has Been Drained & Leg Currently Being Drained PNO-II-88-015, on 880229,licensee Informed NRC That Unit,A 1 Mwt Pool Reactor Had Been Shut Down Due to Primary Coolant Leak Outside Containment.Region II Has Dispatched Both Health Physics & Operations Inspector to Review Event1988-03-0101 March 1988 PNO-II-88-015:on 880229,licensee Informed NRC That Unit,A 1 Mwt Pool Reactor Had Been Shut Down Due to Primary Coolant Leak Outside Containment.Region II Has Dispatched Both Health Physics & Operations Inspector to Review Event ML20150B2371988-02-23023 February 1988 Exam Rept 50-297/OL-88-01 on 880202-03.Exam Results:One of Two Reactor Operators Passed Written Exam & Operating Exam & Senior Reactor Operator Passed Both Exams PNO-V-88-013A, on 880114,reactor Bldg Overpressurization Occurred.Investigation Revealed That High/Low Pressure Trip Circuit for Train 'B' Fan Trip Circuit Inoperable.Licensee Continuing Investigation to Determine Root Cause1988-02-19019 February 1988 PNO-V-88-013A:on 880114,reactor Bldg Overpressurization Occurred.Investigation Revealed That High/Low Pressure Trip Circuit for Train 'B' Fan Trip Circuit Inoperable.Licensee Continuing Investigation to Determine Root Cause ML20235W0801987-10-0909 October 1987 Notice of Violation from Insp on 870929-30.Violation Noted: Operating Procedures for Radiation Control Not Written &/Or Followed for Listed Incidents ML20235W0881987-10-0707 October 1987 Insp Rept 50-297/87-03 on 870929-30.Violations Noted. Major Areas Inspected:Internal & External Exposure Control & Assessment,Control of Radioactive Matl & Contamination, Surveys,Monitoring & Transportation of Radioactive Matl ML20206D3851987-04-0202 April 1987 Notice of Violation from Insp on 870316-18 IR 05000297/19870011987-03-27027 March 1987 Insp Rept 50-297/87-01 on 870316-18.Violations Noted:Failure to Post Required Documents,Failure to Comply W/Dot Requirements for Transportation of Radioactive Matls & Failure to Verify Authorization of Intended Recipient IR 05000297/19860021986-06-0404 June 1986 Partially Withheld Insp Rept 50-297/86-02 on 860521-22 (Ref 10CFR2.790 & 73.21).No Noncompliance Noted.Major Areas Inspected:Plans & Procedures,Safeguards Events Repts & Low Strategic Significance SNM Fixed Physical Protection ML20211A4381986-05-19019 May 1986 Exam Rept 50-297/OL-86-01 on 860423-24.Exam Results:All Five Candidates Passed Oral & Written Exams IR 05000297/19860011986-05-14014 May 1986 Insp Rept 50-297/86-01 on 860414-18.No Violation or Deviation Noted.Major Areas Inspected:Biennial Research Reactor Insp,Including Logs & Records,Review & Audit, Requalification Training & Procedures IR 05000111/19820021982-04-21021 April 1982 IE Insp Repts 50-111/82-02 & 50-297/82-01 on 820315-19. Noncompliance Noted:Control Room Left Unattended & Reactor Safeguards Advisory Group Not Convened Semiannually ML20054H0981982-04-21021 April 1982 Notice of Violation from Insp on 820315-19 IR 05000160/19780041978-10-20020 October 1978 IE Inspec Repts 50-160/78-04, 50-276/78-02, 50-297/78-04 & 70-0386/78-04 on 780926-27 During Which No Items of Noncompliance Were Noted.Major Areas Inspec Incl:Nuc Matl Control & Accounting Procedures Review IR 05000297/19780031978-10-0202 October 1978 Inspec Rept 50-297/78-03 on 780817 During Which No Items of Noncompliance Were Noted.Major Area Inspected:Physical Security Plan 1999-03-02
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ENCLOSURE 1 EXAMINATION REPORT 297/0L-88 Facility Licensee: North Carolina State University Raleigh, NC 27695-7909 Facility Name: North Carolina State University Facility Docket No.: 50-297 Written examinations and operating tests were administered at North Carolina StateUniversitynearRaleigh,NorthCaropna.
Chief Examiner: f )[j WiMiain M. Dean M N i 1 Nf[
Date Signed Approved by: ,bl lllM /[ % l7 dk M4KenethE"Brockman,' Chi ~efOperator ) ate Signed Licensing Section 2 Sumary:
Examinations on February 2-3, 1988.
Operating and written tests were administered to two Reactor Operator (RO) and one Senior Reactor Operator (SR0) candidates; one of two R0's passed the written examination; one of two R0s pas ed the operating examination.
The SR0 passed both examinations.
Based on the results described above, the SR0 passed, while neither R0 passed.
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8803160249 880304 PDR ADOCK 05000297 V DCD
REPORT DETAILS
- 1. Facility Employees Contacted:
- G. D. Miller, Associate Director
- S. M. Grady, Chief Reactor Operator T. C. Bray, Reactor Operations Manager
- 2. Examiners:
- W. M. Dean R. S. Baldwin M. E. Ernstes
- 3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided S. M. Grady, Chief Reactor Operator, with a copy of the written examination and answer key for review. The NRC Resolutions to facility coments are listed below,
- a. SR0 Exam (Applicable R0 questions are in parentheses)
(1) Question 1.06 (G.05)
Agree with the facility coment. Points will not be deducted >
for including "2. (Beta)" as an additional answer to part (a).
(2) Question I.13 (G.08)
Facility coment acknowledged. Since it is possible to have airborne spills in areas other than hoods, the answer key will be changed to have "close hood door" in parentheses to indicate optional information not required for full credit. The candidate must include information analogous to the answer key to receive full credit, as these are Immediate actions contained within the Department of Nuclear Engineering, Laboratory Safety Manual.
(3) Question J.05 (B.05)
Agree with the facility coment. The recomended answer will be considered as an alternate correct response.
(4) QuestionJ.11(a)(C.08(a))
Facility coment acknowledged. Since possible confusion could have resulted from misleading information in the question, this part of the question will be deleted from the exam.
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(5) Question K.04 Agree with the facility comment. Since insufficient information was provided in the question, part (3) will be deleted.
(6) Question K.05 (b) (C.02 (b))
Agree with the facility coment. The answer key will be changed to remove EE.
(7) Question K.05 (c) (C.02 (c)) ,
Agree with the facility coment. The answer key will be changed to remove "/MW".
(8) Question K.15 Agree with the facility coment. The answer key will be modified as recomended.
(9) Question L.10 Agree with the facility coment. The answer key will be modified as recomended.
(10) Question L.12 (C.09)
Disagree with the facility coment. Technical Specifications give tt.e limit as 3% delta K/K, therefore an answer of -3000 pcm could not be a complete answer since this would not deal with experiments involving positive reactivity,
- b. R0 Exam (1) Question A.10 (a & b)
Agree with the facility coment. Since the fast fission factor is fixed after the fuel is fabricated and it is difficult to calculate, this question will be deleted from the exam.
(2) Question A.11 Disagree with the facility coment. This question specifically asks for the functions of installed sources and in no way elicits answers concerning regenerative sources. The recomended facility answer is equivalent to parts (a) and (c) of the answer key. No change to the answer key is justified.
(3) Question B.03 Agree with the facility coment. The answer key will be changed to also read ALERT.
. 'c. . ,
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(4) Question B.07 Agree with the facility comment. The recommended answer will be considered as an alternate correct response.
(5) Question C.04 Agree with the facility comment. The recommended answer will be considered as an alternate correct response.
The typographical error in answer (c) will be corrected to read 1.20 MW (6) Question 0.02 Disagree with the facility comment. "Drive Inhibits" are considered to be "automatic protective signals". It is within the scope of the operator's knowledge to be able to distinguish when an automatic function should or should not take place as is in the case of the Channel Inoperative Inhibit. It is also recommended that the facility revise their reference material to reflect the same terminology throughout, so all operators are able to communicate using common terms. No change to the answer key is justified.
(7) Question D.03 Facility coment acknowledged. The facility's recommended answer is equivalent to the answer key. No change will be made to the answer key.
(8) Question D.09 Disagree with the facility comment. In order for an operator to discern if a control system is functioning properly, he should know what factors cause the controller to actuate. It is within the scope of an operator's knowledge to be able to describe how a controller works in simple terms. No change to the answer key is necessitated.
(9) Question E.01 (b)
Facility comment acknowledged. Since possible confusion could have resulted from misleading information in the question, this part of the question will be deleted from the exam.
(10)QuestionF.01(c)
Disagree with the facility comment. The PULSTAR procedure for ECP calculations specifically states that Power Defect is considered, however, it neglects to state that it is taken to be zero. The facility is encouraged to revise its reference material to reflect this. No change to the answer key is necessitated.
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4 (11) Question F.06 Facility comment acknowledged. The facility's recommended answer (1) will be accepted as an additional alternate answer. However, the facility's recommended answer (2) is equivalent to the answer key.
(12) Question F.07 Facility comment acknowledged. The facility's recommended answer is equivalent to the answer key. No change will be made to the answer key.
- 4. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination.
There were two generic weaknesses noted during the oral examination.
The areas of below normal performance were: Use of procedures and R0 familiarity with the Emergency plan.
The cooperation given to the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations was also noted and appreciated.
The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners, i
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