IR 05000029/1987012

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Insp Rept 50-029/87-12 on 870810-14.No Violations or Deviations Noted.Major Areas Inspected:Nonlicensed Staff Training & Followup on Previous Insp Findings
ML20237K255
Person / Time
Site: Yankee Rowe
Issue date: 08/27/1987
From: Eapen P, Oliveira W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20237K225 List:
References
50-029-87-12, 50-29-87-12, NUDOCS 8709040275
Download: ML20237K255 (7)


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. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-029/87-12 Docket No. 50-029 License No. DPR-3 Licensee: Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701 Facility Name: Yankee Nuclear Power Station { Inspection At: Rowe, Massachusetts l l Inspection Dates: . August 10-14, 1987

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Inspector:

  (' Aliveira, Reactor Engineer
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y u (v #te / 7/ Follow-Up On Previous Inspection Findings (Closed) 50-029/85-01-01 Ur. resolved Item - Licensee did not implement any of the recommended training program effectiveness guidance previded in AD-50 The licensee has incorporated the training program guidance into the { departmental procedure OP-0514, Training Program Development. The 1 inspector verified that the effectiveness guidance was being implemented by reviewing the licensee's actions regaraing selected LERs, training records, and NRC Bulletins and Information Notices. The licensee is ) drafting a new departmental procedure that will specifically deal with and j expand on training effectiveness. This item is close j l

 (Closed) 50-029/85-C1-02 Unresolved Item - Licensee did not have a formal l training program for maintenance engineer The licensee developed and implemented procedure DP-0900, Maintenance Support Department Training. The Training Department has submitted a Self l Evaluation Report (SER) to INPO for the Technical Staff and Managers (TS&M) Training Program that includes the training of engineering personnel. The SEI is required prior to INP0 performing on-site visits i that lead to accreditation. The inspector reviewed the program with the Maintenance Support Department Head who also authored the procedur The i

inspector verified the implementation of DP-0900 by reviewing a modifica-l tion package with a maintenance engineer. This item is closed.

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..      3 (Closed) 50-029/85-01-03 Unresolved Item - Licensee did not have a formalized shelf life progra The inspector "erified that commitments described in follow up NRC Inspection Rerort 50-029/86-17 were completed. Verification included a visit to the warehouse and observing replacement and disposition of expired shelf life material. This item is close . Nonlicensed Training 3.1 Requirement 10Cr950, Appendix B Criterion II, requires in part that a licensee Quality Assurance (QA) program shall provide for indoctrination and training of personnel performing activities affecting quality as necessary to assure that suitable proficiency is achieved and maintaine The Technical Specifications (TS) Section 6.4 requires that training and qualifications of plant personnel be in accordance with ANSI-N18.1-1971 " Selection and Training of Nuclear Power Plant Per-sonnel," and TS Section 6.5.2.9.b requires training to be audited annually. Additionally the QA Manual commits the licensee to ANSI N45.2.6-1978, " Qualification of Inspection Examination and Testing Personnel..."

3.2 Scope The effectiveness of the implementation of the licensee's nonlicensed staff training program was assessed by reviewing the activities in operations, maintenance (mechanical, electrical, and instrument and controls), engineering, and quality assurance (QA) and quality con-trol (QC) area .3 Details of the Review For each of the job functions selected, the inspector reviewed applicable implementing Administrative and Training Department Pro-cedures, qualification and experience of personnel, qualification and training of instructors, and the quality of the on the job training (0JT), to understand and assess the effectiveness of training as evidenced in daily activities. The comments and evaluations from the trainees, line supervisors, and instructors were also reviewed to established how this feedback was factored into future trainin Management and QA involvement in the training area was assessed for effectiveness. No violations or deviations were identified.

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l The inspector reviewed shift turnovers and routine rounds by non-f

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licensed operator (NL0s); and routine activities by engineers, electricians, mechanics, instrument and controls (I&C) technician and Shift Technical Advisors (STAS). The activities were conducted in accordance with the procedures by personnel knowledgeable in the requirements of the procedures and technical specifications. The inspector wi+nessed additi'nal work activities as detailed belo .4 Observation 0; Work Activities The inspe-ta observed an auxiliary operator (AO) instructing a trainee in the primary rounds, e.g. , Primary Auxiliary Buildin The A0 was knowledgeable of his rounds and thorough in his explanation

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of each observation and in the manner in which each observation is recorded and reported. Another A0 described the assistance that

.. supervisors provided, on their own time, to prepare an A0 to take the state examination for Assistant Nuclear Power Plant Operators. This exam has become a prerequisite for reactor operator candidate The inspector observed an STA and shift supervisor reviewing emergency procedure OP 3116 during the 1600-2400 shift. They were discussing the logic chain regarding the loss of control rod breaker trip circui This exercise was in preparation for the planned training to be conducted the next evening. Another STA was develop-ing questions and problems for a lesson plan regarding critical position and shutdown calculations. The STA was a former teacher and was assisting the Training Departmen The inspector observed an electrician conducting weekly checks of the station batteries in accordance with OP 4500. The electrician noted that the hydrometer his assistant was using had a calibration sticker with an overdue date. The electrician immediately stopped the work, sent the assistant to get a calibrated hydrometer, and then started the weekly check from the beginnin The inspector attended a part of a presentation by the Health and Safety supervisor on the use of an oxygen monitor. The subject was attended by maintenance personnel and was well presented. The supervisor explained later that the presentation was done as the result of a plant employee suggestion to the Joint Plant Safety Committee. A specific procedure is being drafted and oxygen deficient spaces will be properly poste The inspector and a Maintenance Support engineer walked down the equalizer line for venting the Safety Injection (SI) Accumulator (Plant Design Change Request (PDCR) 86-001). He was knowledgeable of the need to assure that the PDCR considered the need for training, reviewed the draft of the affected Procedure OP-2676, approved the changes in the body of the procedure, and is reviewing the attached

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diagrams to the procedure. A reactor engineer discussed with the inspector the preparation of the Quarterly Plant Performance data

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p .. 5 1 for submittal to INP0. He was knowledgeable of how useful this data was to the Training Program.

, ' An I&C technician was observed performing OJT with a trainee (tester) during the test of VD-F1-1 SG-2 Blowdown Alarm. The test was con-ducted in accordance with paragraphs 4-8 of OP-4679. After the trainee had been instructed in a specific step in the procedure, he initials the step which becomes a record of OJT qualifications status. The I&C supervisor was observed reading NUREG/CR-2000, Licensee Event Report (LER) Compilation, to provide inputs for the formal and continuing I&C training as well as OJT training to the Training Departmen .5 Training Policy and Progress In April 1987, a new Training Manager was assigned to head the Training Department. The new Training Manager reports to the Plant Superintendent and is responsible for non licensed technical trainin One of first actions taken by the new Training Manager was to request a QA audit of the Training Department's compliance to NRC and INP0 requirements. The Training Department is assessing the results of the audi In March 1986 the Training Department received INP0 Board Accredi-tation for Nonlicensed Operators, Reactor Operators, and Senior Reactor Operators. INP0 assist visit is scheduled for September 1987 and the Accreditation Team visit for the remaining six training areas is scheduled for November 1987. These six training areas are: Electrical Maintenance, Mechanical Maintenance, Instrument and Controls (I&C) Technician, Shift Technical Advisor (STA), and Technical Staff and Managers (TS&M).

Management has approved and budgeted for the expansion of the Training Center. The expansion program should be completed by October 198 The training staff of approximately twenty two instructors, ) supervisors and management administer the technical training program

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for approximately 140 students that includes supervisory personne It is the objective of management to fill all the positions in the non licensed staff training with licensee personnel. Tne licensee is actively recruiting to fill the last two vacancie , During the refueling outage, the Training Department instructors augmented the plant staff. With management's permission the instruc-tors also assessed and reviewed the training needs and formally recommended improvements to their respective programs. The Training Manager is reviewing the recommendation The inspector reviewed the training records of the personnel involved in the inspection. The records are current, complete, readily acces-sible and in compliance with requirement )

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,       6 The nonlicensed training and qualification _. 'ectiveness is measured by the licensee primarily through student and instructor evaluations, and supervisory feedbac The Training Department is preparing a new procedure to deal specifically with the training effectiveness effort which was previously described in DP-0514. QA audits and QA surveillance provide a secondary means for measuring the effective-ness of personnel training and qualification .6 QA/QC Interface With Yankee Rowe Training The annual 1985 and 1986 QA audits and evaluations addressing training were reviewed and discussed with QA and Training Depart-ment representatives. The audits were thorough and comprehensive, and all the identified deficiencies were corrected in a timely manner. QA performed 81 surveillance in 1986 and 86 surveillance in 1987, however, they did not deal specifically with trainin The inspector was presented with a schedule for the balance of 1987 which shows future QA surveillance planned for Security / Training and Qualification Program, Maintenance of Training Records Program, and Maintenance Electrical Training Progra I The inspector discussed with the QC inspectors their role in processing the Maintenance Requests (MRs) observed being used by Maintenance and I&C personnel. The QC inspectors were knowledgeable of the procedural requirement . Management Meetings Licensee management was informed of the scope and purpose of the inspec-tion on August 10, 1987. The findings of the inspection were discussea with the licensee representatives durirg the course of the inspection and presented to licensee management at the August 14, 1987 exit interview (see Paragraph I for attendees).

At no time during the inspection was written material provided to the licensee by the inspector. The licensee indicated that no proprietary information was involved within the scope of this inspectio ' I 'JJ . ' -

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