IR 05000317/1987004

Insp Repts 50-317/87-04 & 50-318/87-04 on 870223-27.No Violations or Deviations Identified.Major Areas Inspected: Nonlicensed Staff Training

ML20206C782
Person / Time
Site:	Calvert Cliffs
Issue date:	03/27/1987
From:	Eapen P, Oliveira W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20206C756	List: IR 05000317/1987004 ML20206C751
References
50-317-87-04, 50-317-87-4, 50-318-87-04, 50-318-87-4, NUDOCS 8704130159
Download: ML20206C782 (7)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report Nos. 50-317/87-04 50-318/87-04 Docket No License Nos. DPR-53 DPR-69 Licensee: Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Facility Name: Calvert Cliffs Nuclear Power Plant, Units 1&2-Inspection At: Lusby, Maryland Inspection Dates: February 23-27, 1987 Inspector: MM W. Oliveira, React 6r Engineer, DRS da'te d 7/[7 '

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Approved by: d-Dr. P. K. Eapen,' Chief, Quality Assurance O 07/N7 date Section, Operations Branch, DRS, RI Inspection Summary: Routine unannounced inspection on February 23-27,1987 (Report Nos. 50-317/87-04,50-318/87-04).

Areas Inspected: Non Licensed Staff Training Results: No violations or deviations were identifie SY $5000yn PDR

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l DETAILS 1. Persons Contacted

• A. Anuje, Supervisor Quality Assurance (QA)

J. Belzer, Supervisor Training Support

• Bowman, General Supervisor, Technical Services Engineering

• J. Carroll, General Supervisor, QA R. Douglass, Manager, QA and Staff Services J. Hill, Supervisor, Operations Training S. Jones, General Supervisor, Planning and Support

• L. Larragoite, Engineer, Licensing J. Lemons, Manager, Nuclear Operation Department

• K. Nietmann, General Supervisor, Nuclear Training W. Putman,' Senior QA Auditor

• P. Rizzo, Supervisor, Maintenance Training

• L. Salyards, Engineer, Licensing

• R. Sheranko,-General Supervisor, Mechanical Maintenance A. Vogel, Supervisor, Technical Training United States Nuclear Regulatory Commission

• T. Foley, Senior Resident Inspector,

• Denotes those who attended the exit meeting on February 27, 1987. Non Licensed Training 2.1 Requirement 10 CFR 50, Appendix B, Criterion II, requires in part that a licensee's 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 .2 Scope

.The effectiveness of the implementation of the licensee's non-licensed staff training program was assessed by reviewing the following activities in the operations, maintenance (mechanical, electrical and control), engineering, and quality assurance (QA)

area Shift turnovers for non licensed operators (NL0s);

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NLO conducting auxiliary building rounds;

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Nuclear plant operator (NPO) qualifying a senior plant operator (SPD) in auxiliary building;

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A SP0, with control room permission, charging the gas barrier between containment and electrical penetrations with nitrogen;

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A training coordinator instructing new control technicians in accordance Electrical & Controls (E&C) Section Guideline 71, Qualification Program;

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A senior controls technician (nuclear) qualifying a control technician to perform a surveillance test procedure (STP)-M-213-1;

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E&C activities such as calibration of power range nuclear instruments in accordance with STP-M-213-1;

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QA audits, preparation of Calvert Cliffs Event Reports (CCERs),

and QC inspectors witnessing work on safety related equipment;

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Engineering activities in processing Facility Change Requests (FCRs) .

2.3 Details of the Review For each of the activities identified in paragraph 2.2, 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 trainin Management and QA involvement in the training area were assessed for effectivenes .4 Observation of Work Activities The inspector witnessed the work activities identified in paragraph 2.2 as detailed below. The activities were conducted in accordance with the procedures by personnel knowledgeable in the requirements of the procedures and technical specification The inspector observed the qualification by a NPO of a SP0 to perform auxiliary building rounds. They reviewed in detail the survey maps with the radiation control technician prior to conducting the rounds. The SPO continually kept the control room advised as to the status of nitrogen charge to the electric canisters for maintaining the gas barrier between the containment and the electrical penetration _ , _ - . _ . _ - , - .- -,_ .

The inspector observed a senior mechanic instructing a mechanic and trainee in the removal and inspection of the failed inboard bearing to the Service Water Pump no.11. The senior mechanic also discussed the bearing problem with the engineer and the Metals Laboratory representativ The senior mechanic walked down the job with .the inspector. The work was performed in accordance with Maintenance Order 206-345-518B. Another senior mechanic was observed instructing a trainee to reset the clearance of the turbine governor in accordance with paragraphs 2,3,&4 of preventive maintenance (PM)

procedure 2-36-M-SA- The inspector witnessed the calibration of the power range nuclear instruments. The control technicians stopped the calibration effort when they noted that Channel Y reading was 0.2261 instead of 0.0825 millivolts. Channel Y indicates the difference of the upper and lower excore detectors from the incore readings. The technician reviewed several drawings and the technical manual. They concluded that other inputs (such as power levels) affected the reading. They discussed their conclusions with supervision and obtained permission to continue the calibration in accordance with STP-M-213-1. They also i found a typographical error in the procedure. Supervision reported to the inspector that the error was previously reported and was being correcttd by the procedure development group. The inspector also observed the trainee researching the drawings and technical manual in assisting the control technicians. The trainee was being qualified in the Reactor Protection System and Surveillance Test Procedure The E&C OJT training coordinator was observed conducting class for new hires in the E&C shop. The class was being conducted in accor-dance with E&C Section Guideline 71, E&C Qualification Program. The training coordinator was also observed at the Training Center instructing personnel on the RTD loop FTI-103 and 106 recording instrument The inspector walked down FCR 84-1094 and FCR 85-1048 with two en-gineers. These FCRs were prepared and processed in accordance with CCI 126G, Facility Change Request, Administrative Control . FCR 84-1094 modified the Auxiliary Feedwater (AFW) Flow Control and Recir-culation Valves. Attachment (4-F) of CCI 126G contained information requiring requalification of the operators. The Training Section was able to provide evidence that this was performed in the Operators Training, Session 6. FCR 85-1048 replaced the MSIV hydraulic system with a Rockwell International Corporation hydraulic syste Seven-teen personnel from Operations, Mechanical Maintenance, Training and Engineering attended a three day session at Rockwel From this training, lesson plans for NL0s, mechanics and E&C personnel were develope This training was completed during Operator Training, Session . - . -. .- _

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The inspector toured the Training Section Laboratories and discussed the improvements since his last inspection in February 1985. These improvements included: a Reactor Vessel Head Mockup to handle rigging exercises (component removal and replacement facilities for incore instrumentation, flanges, bolting, O rings, cooling shroud, etc)

control valves. for practicing trouble shooting, disassembly, re-building, and testing; and a Chesterton packing mockup developed by the licensee and the manufacturer. The Chesterton packing mockup proved so successful that the manufacturer is adopting the mockup for use in other plant A senior engineer in the QA Department, walked down CCER 87-1 regarding the slow stroke time for AFW-4070 and 4071 valves. The CCER was processed in accordance with CCI-127B, Calvert Cliffs Event Reports. Several experts were involved in the resolution of the CCE One engineer wrote a safety analysis of elastomers and another

engineer wrote a modification (FEC 79-1062-489) for the installation of solenoid valves. The inspector interviewed one of the component engineers as to his involvement and training to perform the functio >

This engineer was knowledgeable and adequately trained. Another CCER (87-2) regarding loss of instrument air followed by a manual reactor trip, was in the investigation stage. The preparer walked down the investigation effort with the inspector. The effort was in compliance with CCI-1278.

2.5 Training Policy and Progress The General Supervisor of the Nuclear Training Section at Calvert Cliffs is responsible for non licensed trainin The General Supervisor reports to the Manager of Quality Assurance and Staff Service An INPO Accreditation Board visit is scheduled for March 26, 1987 to review training programs for Electrical and Mechanical Maintenance Mechanics, Instrument and Control Technician, Shift Technical Advisor, and Technical Staff and Manager The other training programs have already been accredited by INP The key procedures for the Non Licensed Training Program include:

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CCI 603D, Plant Operator Training & Qualification,

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CCI 6060, Maintenance Personnel Training,

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CCI 609B, Training Program for Engineering an Technical Staff,

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Training Instruction (TI) -20, Maintenance Training Programs,

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Hiring a contractor to develop E&C Maintenance training materials and Systems Engineer Training materials, the development of Mechanical Maintenance Training materials and the development of the Integrated Corrective Action Program (ICAP) to enhance the effectiveness of corrective action systems are some of the examples of management support in training area Additionally, Plant Operating Safety-Review Committee (POSRC) Outstanding Items List tracked training need Staffing of the Training Section is adequate to instruct the facility's 520 non-licensed personne They have approximately 25 instructors on board and are actively filling all vacancie The inspector reviewed the training records of the instructors and other personnel involved in this inspectio The records are current, complete, readily accessible and in compliance with ANSI N45.2.6.

Management measures training and qualification effectiveness using Non-Conformance Reports (NCRs), QA Audits, CCERS, and LER The Training Section additionally has their own means of measuring effectiveness (e.g. critiques from the students, supervision, and peer and supervisory appraisals of instructors). The plant operator instructors spend three months / year at the plan Maintenance

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instructors work with mechanics during outages to provide 0J .6 QA/QC Interface With Calvert Cliffs Training QA audit . reports 42.2-85-36, -86-11, -86-37, 20-30- 85 and -38-85 addressing training were reviewed and discussed with a QA represen-tativ The audits were thorough and comprehensive, and all the findings were corrected in a timely manne The inspector observed a QC inspector following the removal of the inboard bearing to number 11 Service Water Pump and the subsequent analysis of the cause of the problem. The QC inspector was knowledge-

• able in the requirements of the tas The inspector reviewed five NCRs that addressed training deficien-cies. None of these NCRs were formally provided to the training deps.rtmen This item remains unresolved pending a review of the licensee's implementation of a system to provide training-related NCRs to the training department (50-317/87-04-01 and 50-318/87-04-01).

2.7 Conclusion

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No violations were identified. The licensee's non-licensed training program is implemented in accordance with NRC requirements and licensee commitment . - - _ - __ .-.

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7 Unresolved Items Unresolved Items are matters about which more information is required to ascertain whether they acceptable items or violation One unresolved item is discussed in paragraph . Management Meetings Licensee management was informed of the scope and purpose of the

. inspection at the entrance interview on February 23, 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 February 27, 1987, exit interview (see paragraph 1 for attendees)

At no time during the inspectirn was written material provided to the l licensee by the inspectors. The licensee indicated that no proprietary information was involved within the scope of this inspection.