IR 05000333/1987017

Insp Rept 50-333/87-17 on 870511-15.No Violations or Deviations Noted.Major Areas Inspected:Nonlicensed Staff Training & Licensee Action on Previous NRC Findings

ML20214T337
Person / Time
Site:	FitzPatrick
Issue date:	05/29/1987
From:	Eapen P, Oliveira W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20214T322	List: IR 05000333/1987017 ML20214T321
References
50-333-87-17, NUDOCS 8706100212
Download: ML20214T337 (6)

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A i- U.S. NUCLEAR REGULATORY COMMISSION

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REGION I

Report N /87-17 Docket N '

License No. DPR-59 Licensee: Power Authority of the State of New York P.O. Box 41 Lycoming, New York Facility Name: James A. FitzPatrick Nuclear Power Plant Inspection At: Scriba, New York Inspection Dates: May 11-15, 1987 Inspector: 4 5/f/67 (f.Oliveira,RpctorEngineer,DRS ' d' ate Approved by- ~Mk Vr gP. K. Eapen,' Chief, Quality Assurance 3/ T9 pe '7 Section, Operations Branch, DRS, RI

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Inspection Summary: Routine unannounced inspection on May 11-15,1987. (Report No. 50-333/87-17).

i Areas Inspected: Non Licensed Staff Training and Licensee Action on Previous

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NRC Findings.

J Results: No violations or deviations were identified.

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DETAILS 1. Persons Contacted

• R. Baker, Maintenance Superintendent

• R. Converse, Resident Manager

• J. Erkan, Senior Plant Engineer Supervisor

• W. Fernandez, Superintendent of Power

• 4. Keith, Instrument and Control Superintendent

• D. Lindsey, Operations Superintendent R. Locey, Assistant Operation Superintendent

• P. LoTempio, Finance and Administration Manager

• E. Mulcahey, Radiological and Environmental Services Superintendent

• R. Patch, Quality Assurance Superintendent

• D. Simpson, Training Superintendent United States Nuclear Regulatory Commission A. Luptak, Senior Resident Inspector,

• Denotes those who attended the exit meeting on May 15. 198 Other plant personnel were interviewed during the course of this inspectio . Non Licensed Training 2.1 Requirement 10 CFR 50, Appendix B Criterion II, requires in part that a licensees 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 Specification Section 6.4 requires that retraining and replacements be in accordance with ANSI N18.1-1971, " Selection and

, Training of Nuclear Power Plant Personnel". Additionally FSAR Chapter 13 commits the licensee to Regulatory Guide 1.58, Qualifications of Inspection, Examination and Testing Personnel" which endorses ANSI

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j j N45.2.6 197 ;

l i 2.2 Scope j The effectiveness of the implementation of the licensee's non l licensed staff training programs was assessed by reviewing the activities in operations, maintenance (mechanical, electrical, and instrument and control), engineering, and quality assurance (QA)

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2.3 Details of the Review

. For each of the job functions selected, the inspector reviewed the implementing procedures, qualification, and experience of personnel, qualification and training of instructors, quality of the on the job training (0JT), and the effectiveness of training as evidenced in daily activities. The comments and evaluations from the trainees, line supervisors, and instructors were also reviewed to establish how this feedback was factored into future training. Management and QA involvement in the training area was assessed for effectivenes *

The inspector reviewed shift turnovers, routine rounds by non licensed operators (NL0s), and routine activities by engineers, electricians, mechanics, and instrument and control (I&C) tech-nicians. 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 belo .4 Observation of Work Activities The inspector reviewed an Engineering Change Request (ECR) with the lead plant engineer and the cognizant plant engineer. The ECR was an advance ECR developed and processed in accordance with Engineering and Design Procedures (EDPs) 5, 6 and 16. An advance ECR allows urgent work to be performed prior to completing the revisions of affected technical documentation, e.g. drawings. The lead plant engineer provided OJT to the cognizant plant engineer in processing the sdvance EC NLO3 were observed by their shift supervisors during the performance of seekly surveillance tests (STs) of the Fire Protection System and the Battery Ventilation Equipment, as well as the quarterly ST cf the Reactor Building Exhaust Monitoring Instrument / Isolation Logic System Functional Tests. During the weekly STs the inspector observed a NLO report a leakage from the diesel fire pump packing gland to the Contrii tic am. The NLO also initiated a Work Request (WR) 54485 to correct the proble An ICC technician and apprentice were replacing a low oil pressure timing ralay to the air conditioning unit of the LPCI-A pump. The installation and test of the timing relay was performed in accordance with of WR 66/50737. Another I&C technician and apprentice were observed modifying a signal distribution module 275DM-101B in the Torus Pressure Instrument panel in accordance with ECR F1-82-021-240. In both case the inspector observed that the technicians were #

providing OJT to the apprentice .

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2.5 Training Policy and Progress The Superintendent of the Training Department is responsible for non licensed trainin The Superintendent reports to the Resident Manage In October 1986, the Training Department received INPO Board Accreditation for Non Licensed Operators, License Replacement, and Licensed Operator Requalification. An initial INP0 Team visit was conducted in February 1987 to review the remaining seven training areas. A second INP0 Team visit is scheduled for July to complete this review. The remaining seven training areas are: Shift Technical Advisor; Instrument and Control Technician; Electrical Maintenance; Mechanical Maintenance; Radiological and Environmental (includes Chemistry); and Technical Staff and Managers. The licensee expects INP0 Board action in the Fall of 198 The key procedures for the Non Licensed Training Program include:

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Nuclear Training Department Training Procedures Boo Administrative Procedure (AP) No. 9.1, " Preparation, Review and Approval of Indoctrination and Training Procedures."

On July 25, 1985, the licensee and the union ratified an agreement for the four year Apprentice Program that was officially implemented in March 1986. Also the Qualification Cards and Standards were issued in March 1986. Formal training however began as early as January 1984. During the visit in February 1987, INP0 reviewed the Apprentice Program's prerequisites and qualifications. A six week Fundamentals course for new apprentices was developed at the recommendation of the INP0 Team. Technical Staff and Manager training will start in late June 198 The non licensed training staff of approximately twenty instructors, supervisors and management administer the training program and instruct a student body of 220 NL0s, craft, technical, and super-visory personne The training records of the personnel involved in this inspection were reviewed. These records are in compliance with the FSAR, ANSI N45.2.6 and N45.2.9. The records are current, complete and readily accessibl The non licensed training and qualification effectiveness is measured by the licensee primarily through student and instructor evaluations, supervisory feedback and Training Committees. QA audits and surveillances provide a secondary means for measuring the effective-ness of personnel training and qualification __ - - - _ . _ _ _ _ _ __

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2.6 QA/QC Interface With Non Licensed Training Program Seven 1986-87 site QA audit reports addressing non license training were reviewed and discussed with a site QA representativ The audits are in addition to the criterion QA audits conducted annually for the Safety Review Committee in accordance the Technical Specification paragraph 6.5.2. The audits were thorough and comprehensive, and all the findings were corrected in a timely manner. All except the corrective actions for two findings were verified by QA. A site QA audit will be scheduled in 1987 to audit the NLO Training Are Four 1986 QA surveillance reports were also reviewed with the site QA representativ The QA representative stated that the auditors addressed the qualifications and training of personnel while surveilling an activity. The surveillance findings were corrected in a timely manne Only one finding is awaiting QA verificatio The inspector observed the QC inspector for I&C work following the surveillance tests (STs) of the timing relay in panel 66PNL-1A, the Main Stack Exhaust Process Radiation Monitor, and the signal distribution module 27SDM-1018. The QC inspector was knowledgeable in the requirements of the ST tasks. In preparing for the ST of 27SDM-1018, the QC inspector noted that the crimping tool was out of calibration. The technician obtained a properly ca'ibrated crimping tool prior to commencing the jo .7 Conclusion No violations were identified. The licensee's non licensed training program is implemented in accordance with NRC requirements and licensee commitment .0 Licensee's Action on Previous NRC Concerns (Closed) Unresolved Item (50-333/82-22-02): Lack of data in the training record The inspector verified through review of 25 personnel training records that the records are correct and a computerized matrix exists to track progress. Also QA audits of training records were reviewed and all findings were corrected and verified by Q Based on the review of the licensee's action, this item is close (Closed) Inspector Followup Item (50-333/83-06-05): Training records are not stored in accordance with ANSI N45. The inspector verified through review of 25 personnel training records and review of licensee's QA audits that the records are now in compliance with ANSI N45. .

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Based on the review of the licensee's action, this item is close (Closed) Inspector Followup Item (50-333/84-02-02): Short term BWR Technology course not implemente The inspector noted during the review of the persernel training records that the short term course has been replace The records contained evidence of attendance and scores for the permanent BWR cours Based on the review of the licensee's action, this item is close (Closed) Unresolved Item (50-333/85-13-01): Excessive backlog of QC Inspection Reports (QCIRs).

Licensee has computerized the tracking of QCIR QC personnel are assigned to the Workload Center to expedite the QCIR The inspector reviewed the automated (computerized) records since January 1987. Of the 962 QCIRs tracked, only six of the 125 outstanding reports were older than the 90 day period definition for overdue QCIR Based on the review of the licensee's action, this item is close (Closed) Unresolved Item (50-333M6-11-02): Lack of procedure for implementing QC Receiving Instructions (QCRIs).

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Implementing procedure QA Instruction (QAI) 7.0 was issued on September 2,1986, with QCRIs as appendices. QAI and QCRIs were reviewed and found to be adequat Based on the review of the licensee's action, this item is close .0 Unresolved Items Unresolved Items are matters about which more information is required to ascertain whether they are acceptable items or violation Three unresolved items were closed in paragraph .0 Management Meetings Licensee management was informed of the scope and purpose of the a.spection at the entrance interview on May 11, 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 May 15, 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 _ - , _ _ _ ._ _ _ . . _ .- . . - _ _ _ - - _ , _ _ _ - - - _ . . . _ -