IR 05000309/1987018
| ML20238A168 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 08/12/1987 |
| From: | Eapen P, Oliveira W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20238A146 | List: |
| References | |
| 50-309-87-18, NUDOCS 8708200390 | |
| Download: ML20238A168 (5) | |
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'U.S. NUCLEAR REGULATORY COMMISSION i
REGION I
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Report No.
50-309/87-18
Docket No.
50-309 License No. DPR-36 Licensee:
Maine YankAe Atomic Power Company
- 83 Edison Drive
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Augusta, Maine 04336
' Facility Name: Maine Yankee Atomic Power Company Inspection At: Wiscasset, Maine I
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Inspection Dates: July 27-31, 1987,
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T ll, T'1 Inspector':
i W. Oliveira, Rdact3r Engineer date QAS, OB, DRS q
. Approved by:
.M. [
/2 k7 Dr. P. K. Eapen, Chief, Quality Assurance datel
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Section, Operations Branch, DRS,- RI Inspection Summary: Routine unannounced inspection on July 27-31, 1987.
(Report No. 50-309/87-18)
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Areas Inspected: Non Licensed Staff Training and follow up on previous inspection findings.
Results: No violations or deviations were identified, l
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8708200390 870813 PDR ADOCK 05000309 Q
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DETAILS 1. Persons Contacted
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P. Cereste, Instrumentation and Control Instructor S. Evans, Licensing Engineer
- C. Frizzle, Vice President, Manager of Operations
- J. Garrity, Plant Manager T. Gifford, Engineering Section Head L. Lawson, Quality Assurance (QA) Section Head
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Lawton, QA Manager A. Shean, Training Manager United States Nuclear Regulatory Commission
- C. Holden, Senior Resident Inspector,
- Denotes those who attended the exit meeting on July 31, 1987
2.
Follow Up On Previous Inspection Findings (Closed) 50-309/84-18-01 Violation - Licensee did not include all corrective action sources in the audits of corrective action results, i
The inspector verified that all corrective action sources are being audited on a six month frequency through audits and on-site evaluations.
Based on the above, this item is closed.
(Closed) 50-309/86-07-01 Unresolved Item - Licensee was not performing engineering evaluations for adverse effects on items that lacked pre-ventive maintenance.
The inspector verified that the licensee has conducted engineering reviews on all items that lacked preventive maintenance. The results of the evaluation identified mechanical bearing degradation which was corrected.
At the request of the inspector, the licensee revised their procedure number 16-277-1, Revision 2, " Stores Shelf Life & Preventive Maintenance System", to include the requirement for engineering evaluations for adverse effects on items that required and lacked preventive maintenance.
Based on the above, this item is closed.
3.
Non-Licensed Training 10CFR50, 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 maintained.
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i The Technical Specification Sections 5.3 and 5.4 require that training and qualifications of plant personnel be in accordance with ANSI N18.1-1971, l
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" Selection and Training of Nuclear Power Plant Personnel", and Section 5.10.2.h requires training to be audited annually. Additionally the QA Manual commits the licensee to Regulatory Guide 1.58, Qualification of
. Inspection Examination and Testing Personnel" which endorses ANSI N45.2.6-1978
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l 3.1 Details of the Review The effectiveness ~of the implementation of the licensee's non-l
. licensed staff training program was assessed by reviewing the
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activities in operations, maintenance (mechanical, electrical, and
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instrumentation and control), engineering, and quality assurance (QA)
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For each of the job functions selected, the inspen.-.eviewed the implementing procedures as documented in the Training Department i
Training' Manual (TDTM), the qualification and experience of j
personnel, the qualification and training of instructors, and the
quality of the on-the-job-training (0JT) to understand and assess the
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effectiveness of training.
The comments and evaluations of the.
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trainees, line supervisors, and instructors were also reviewed to established how this feedback was factored into future training.
Management and QA involvement in the training area was assessed for effectiveness.
.The inspector observed shift turnovers and routine rounds by non-licensed operators (NLO); and routine activities by engineers, electricians, mechanics, instrumentation and control (I&C) technician and Shift Technical Advisors (STA). The activities were conducted.in accordance with the procedures by personnel knowledgeable in the requirements of the procedures and technical specifications. The inspector witnessed additional work activities as detailed below.
3.2 Observation of Work Activities The inspector observed a nuclear plant operator (NPO) instructing a new trainee during his rounds of the Switch Yard and Relay Building.
The NPO was knowledgeable of his rounds and fully aware that this was
the trainee's first time performing yard rounds.
Another NPO was' observed setting up and providing maintenance with
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demineralized water to wet down the cover over condenser tubes.
The NPO reviewed the procedure for providing the demineralized water with the inspector. The inspector also observed a plant mechanic instructing his mechanics on the importance of assuring that the cover over the main condenser tubes was continually maintained wet.
The plant mechanic explained in detail and with great emphasis that the cover was made of a flammable material and any weld splatter from work on the turbine above could cause a fire if the cover was not maintained we __
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i Another plant mechanic was observed showing the QC inspector the torque wrench settings each time he was going to torque the studs on a flange. The mechanic was required only to show the initial and final settings. His training however taught him to be conservative.
The inspector observed an electrician explaining to his assistant the need to be thorough in drawing a diagram of the emergency diesel generator (EDG) 1A relay STL01 connections. The diagram was required in procedures 5-38-1 and 5-78-1 before disconnecting the leads to the relay for calibration purposes.
3.3 Training Policy and Progress The human Resources Department is responsible for supervisory and management training.
The Manager of the Training reports to the Vice President and Manager of Operations and is responsible for non licensed technical training.
In March 1987 the Training Department i
received INPO Board Accreditation for Non Licensed Operators, Reactor Operators, Senior Reactor Operators, and Radiation Protection Technicians. An INP0 Accreditation Team visit is scheduled in December 1987 for the remaining six training areas. These training arras are: Electrical Maintenance, Mechanical Maintenance, Instrumentation and Control (I&C) Technician, Shif t Technical Advisor (STA), and Technical Staff and Manager.
Management in its quest to have the Training Programs INP0 Accredited has provided space in one of the plant buildings for the construction of maintenance training shops.
The training staff of approximately twenty five licensee instructors, supervisors and management administer the technical training program for approximately 320 students including supervisory personnel. It is the objective of management to continue the non licensed staff training with licensee instructor personnel.
The inspector reviewed the training records of the personnel involved in the inspection. The records are current, complete, readily accessible and in compliance with ANSI N45.2.6.
The non licensed training and qualification effectiveness is measured by the licensee primarily through student and instructor evaluations, supervisory feedback and the Plant Training and Qualification Review Board. The written summary of the Board actions are submitted to the Manager of Operations and the Chief Operating Officer. QA audits and evaluations provide a secondary means for measuring the effectiveness of personnel training and qualifications.
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i 3.4 QA/QC Interface With Maine Yankee Training I
The annual 1986 and 1987 QA audits and evaluations addressing training were reviewed and discussed with QA representatives. The i
audits were thorough and comprehensive, and all the identified deficiencies were corrected in a timely manner.
The inspector observed QC inspectors following the calibration of the EDG 1A relay. During the calibration effort, one QC inspector
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questioned and personally followed up on the lack of calibration
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status of the stop watch used to check the response times. The QC inspector also questioned the Controls and Limits form prepared by the Plant Engineering Department (PED) regarding the proper voltage required to perform the test.
Both questions were expeditiously resolved. Other QC inspectors were observed to be involved in the turbine work as well as maintenance work. The QC inspectors were well versed as to their role in accomplishing the inspections and tests.
No violations or deviations were identified.
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Unresolved Items Unresolved Items are matters about which more information is required in order to ascertain whether they are acceptable items or violations.
One unresolved item was closed during this inspection as discussed in Paragraph 2.
5.
Management Meetings Licensee management was informed of the scope and purpose of the inspection on July 27, 1987. The findings of the inspection were discussed with the licensee representatives during the course of the inspection and presented to licensee management at the July 31, 1987, exit interview (see paragraph 1 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 inspection.
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