IR 05000293/1987024

Insp Rept 50-293/87-24 on 870601-05.No Violations or Deviations Noted.Major Areas Inspected:Nonlicensed Staff Training

ML20216C366
Person / Time
Site:	Pilgrim
Issue date:	06/18/1987
From:	Eapen P, Oliveira W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20216C338	List: IR 05000293/1987024 ML20216C333
References
50-293-87-24, NUDOCS 8706300270
Download: ML20216C366 (5)

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U.S. NUCLEAR REGULATCRY COMMISSION ;

REGION I

Report-No /87-24 l Docket No License Nos. DPR-35 Licensee: Boston Edison Company 800 Boylston Street Boston Massachusetts 12199 Facility Name: Pilgrim Nuclear Power Station Inspection At: Pilgrim, Massachusett Inspection Dates: June 1-5, 1987,  ;

' Inspector: / '

r Oliveira, R'eactor Engineer, DRS dat'e /

J Approved by: @. K - CAbyv 6//h[k7 i Dr. P. K. Eapen, Chief, Quality Assurance datd '

Section, Operations Branch, DRS, RI Inspection Summary. Routine unannounced inspection on June 1-5, 1987 l (Report No. 50-293/87-24) '

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Areas Inspected: Non-Licensed Staff Training Results: No violations or deviations were identifie i

8706300270 870618 PDR ADOCK 05000293 G PDR

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b DETAILS

'1. Persons ~ Contacted'

E '*L. Beckwith,1 Compliance Engineer

• R.; Bird,. Senior Vice President,. Nuclear N. Brossee, Outage Manager

~F...Famulari, Quality Control'(QC) Group Leade E.~ Graham, Training. Staff Assistant

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• S. Hudson, Operation Section Manager

• E. Larsson, Senior' Quality Assurance.(QA)-Engineer-

• A.'Morisi, Test and Turnover Section Manager

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J. Quinn, QA Engineer

• K Roberts, Nuclear Operations Manager

• J. .Seery, Technical Section Manager

• R. Sheery,' Chief-Maintenance Engineer

• A..Shiever, Senior Nuclear Training Specialis ' *E. .Ziemiansk1,1 Nuclear Training Section Manager-United States Nuclear Regulatory Commission

• J. Lyash, Resident Inspector,- -

T. Kim, Resident' Inspecto * Denotes'those who attended the exit. meeting'on June 5, 1987 2.. 'Non-Licensed Training 2.1 Requirement 10CFR50, Appendix B Criterion II, requires in part that a ' licensee j

. Quality Assurance . (QA) program shall' provide for ' indoctrination and 1 training of personnel performing activities. af_fecting quality as l necessary to assure that suitable proficiency 'is achieved and l maintaine j

'l The Technical . Specification Section 6.4 requires that retraining and replacements be in accordance- with ANSI N18.1-1971; " Selection and i Training of Nuclear Power Plant Personnel", and Section B. .:

requires training to be audited annually. Additionally the QA Manual commits the licensee to Regulatory Guide 1.58, Qualification of 1 Inspection Examination and Testing Personnel" which endorses ANSI '

N45.2.6-1978 q

2.2 Scope

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The effectiveness of the implementation of the licensee's non-

-licensed staff training program 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 c procedures as -' documented .in .the: Pilgrim Nuclear Power Station Training Manual, 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 evalua -

. tions from the-trainees,1,ine supervisors, and instructors were also 1 reviewed to ' established how this feedback was factored into future-

' training. Management and QA involvement in. the Et raining area was'

assessed ~for effectiveness. No violations. or deviations were-identifie The inspector reviewed shift turnovers, tours (routine rounds)' by .

non-licensed ope'rator -(NL0s), and routine activities by engineers, electricians, mechanics, instrument and control (I&C) technician and Shif t Technical .' Advisors (STAS). . The activities were conducted 'in ;

accordance . with the procedures by personnel- knowledgeable in th requirements of the' procedures and technical ' specifications. The inspector witnessed additional work' . activities as detailed belo .4 ' Observation of Work Activities The inspector observed the " Tour School Training" at the plant by the Nuclear Training Section instructors. This training was monitored by Training Staff Assistants. Three NL0s . ware observed -simulating a Fire Pump Test in accordance with procedure 8.B.1. The instructor intro-duced scenarios in the conduct of the . test to challenge.the student The ' instructor ' and the students later-discussed . the results of the test. In another' case the inspector observed 'a' NL0' removing breaker ~

tags to return a system to normal condition. He was assisted by a NLO l traine The inspector observed a mechanic shop testing a snubber (SN-0108) in accordance with procedure 3M-4-37 in a radiation area under Radiatio ,

Work Permit (RWP) 87-68). He was well versed in the ALARA require- '

ments as well and the requirements of the procedur The inspector observed a welder being requalified to Brazing Procedure Specification (BPS) P-10H-101 and another welder being qualified to .l the same procedure. Both welders knew the requirements of the procedure and were preparing their weld specimens for tests by the 3 approving examine l An electrician was observed replacing breaker 52-306-MCC B23 in 1 accordance with maintenance request (MR). Another electrician simu- l lated the bypassing of switches to manually fire squib valves CG 85-87, and 93-95 during a Emergency Response drill. The electricians including the drill coordinator who was also an electrician knew the requirements of their tas I

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An I&C technician was observed trouble shooting the pyrotechnics !

alarm to the motor generator (MG) set and the emergency diese {

generator (EDG) in accordance with MR 87-235. The alarm did not i provide enough information to the control room to determine if a-potential fire was at the MG set or the EDG. The technician was preparing a recommendation to engineering for resolving the proble The technician was trained to prepare and process the recommendatio .5 Training Policy and Progress l

The Nuclear Training Section Manager at Pilgrim . reports to the Vice- 4 President Nuclear Operations and is responsible for non-licensed }

trainin In June 1986 the Nuclear Training Section received INP0 !

Board Accreditation for Non-Licensed Operators, Reactor Operat o Senior Reactor Operators, and Radiation Protection Technician. INPO Accreditation Team visit was conducted in December 1987, for the remaining six training areas. These training areas are: Electrical Maintenance, Mechanical . Maintenance, Instrument and Control (I&C)

Technician, Shift Technical Advisor (STA), and Technical Staff and Manager. The licensee's response to the INPO Team visit is in it's final review. The licensee expects to appear before the National Accreditation Board in mid or late summe Apprentice programs for Mechanical, Electrical, I&C, Radiochemistry and Health Physics were approved in May of 198 The first class is scheduled to start July 1,198 Non-licensed training staff of approximately twenty contractor and licensee instructors, supervisors and management administer the

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training program for approximately 120 students including technical and supervisory personne The inspector reviewed the training records of the personnel involved in the inspectio The records are current, complete, readily accessible and in compliance with ANSI N45. ,

i The non-licensed training and qualification effectiveness is measured by the licensee primarily through student and instructor evaluations, supervisory feedback and Training Program Evaluation Committee (TPEC). The Committee was recently reinstated to assure that Pilgrim plant management and supervisory personnel would be more actively I involved in the non-licensed training program. 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 pilgrim Training The annual 1986 and 1987 QA audits addressing training were reviewed and discussed with QA representatives. The audits were thorough and compre-hensive, and all the identified deficiencies were corrected in a timely manne The inspector observed QC inspectors' following the test of snubber SN-0108 (RWP87-68) and DC Backup Battery Charger (MR 87-46-164). The QC inspectors were well versed as to their role in accomplishing the test . Management Meetings i

Licensee management was informed of the scope and purpose of the inspec-

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tion at tha entrance interview on June 1, 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 June 5, 1987, exit interview (see paragraph I for attendces).

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 !

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