IR 05000458/1989001

Insp Rept 50-458/89-01 on 890501-05.No Violations Noted. Major Areas Inspected:Facility Mods & Nonlicensed Staff Training

ML20244C388
Person / Time
Site:	River Bend
Issue date:	06/07/1989
From:	Gagliardo J, Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20244C387	List: IR 05000458/1989001 ML20244C385
References
50-458-89-01, 50-458-89-1, NUDOCS 8906140245
Download: ML20244C388 (8)

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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-458/89-01 License: NPF-47 Docket: 50-458 Licensee: Gulf States Utilities (GSU)

P.O. Box 220 St. Francisv111e, Louisiana 70775 Facility Name: River Bend Station (RBS)

Inspection At: St. Francisville, Louisiana Inspection Conducted: May'1-5, 1989

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Inspector: [2 Ms &f .

p in/R. Hunter, p~nior Reactor Inspector d /

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0$erational PFograms Section, Division of ReactorSafety Approved: !d-u d 61A /

Date p'ames5'.Gagliardo, Chief,OperationalPrograms Section, Division of Reactor Safety Inspection Sungnary Inspection Conducted May 1-5, 1989 (Report 50-458/89-01)

Areas Inspected: Routine, unannounced inspection of facility modifications and nonlicensed staff trainin Pesults: Within the two areas inspected, no violations or deviations were identifie The inspection revealed that the completion and implementation of facility modifications appeared to be fully acceptable. In the area of nonlicensed staff training, based on the specific area reviewed, additional management attention appeared to be warranted to ensure that the training program requirements were fully established with goals and milestones provided and implemente PDR ADOCK 05000458 Q PDC i

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DETAILS

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1. s Persons Contacted

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GSU

• T. F. Plunkett, Plant Manage *D. R. Derborne, Assistant Plant Manager, Maintenance

• J. P. Schippert, Assistant Plant Manager, Operations /Radwaste

• M. F. Sankovich, Manager, Engineering Department

• L. A. England, Director, Licensing

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D. L..Andrews, Director, Nuclear Training

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• T. C. Crouse, Quality Assurance Manager '

• K. E.~ Suhrke, Project Manager

• J. F. Brooker Manager, RBS Oversight

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• H. Odell, Manager, Administration

• G. K. Henry, Director, Quality Operations

• W. L. Curran, Site Representative (Cajun)

• I. M. Malik, Supervisor, Quality Systems

• C.'t. Miller, Senior Compliance Analyst

• J. W. Cook, Lead Environmental' Analyst

• W. J. Fountains, Senior QA Engineer-D. E. Jernigan. I&C Supervisor J. R. Langley, Project Engineer

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J. Ambergey, Project Engineer

• C. B. Mermigas, Project Engineering Coordinator

• C. A. Rohrmann, Training System Coordinator D. Dietzel, Nuclear Training Coordinator R. K. Stoner, Field Engineer J. A. Allen, Nuclear Training Representative I&C NRC

• D. D. Chamberlain, Chief, Reactor Project Section A, Region IV

• E. J. Ford, Senior Resident Inspector

• B. Jones, Resident Inspector-

• R. C. Stewart, Reactor-Inspector, Region IV

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Other members of the technical end administrative staff were also contacte * Denotes those persons attending the exit interview on May 5,198 . Facility Modifications (37701)

The NRC inspector reviewed selected facility modifications made by the-licensee pursuant to 10 CFR 50.59 and provided to the NRC in the routine annual report. The review was conducted to verify that the changes were completed in accordance with the licensee QA Program (Regulatory Guide 1.64/ ANSI N45.2.11-1974) and the Technical Specifications. The

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-3-review of the selected facility changes by the NRC inspector included the initiation, review, and approval, design and design review, installation and testing of the modifications. No facility changes requiring prior NRC approval were noted to have been reportea to the NRC by the licensee. The following modification requests were reviewed:

MR 84 itil5, " Reactor Water Cleanup Heat Exchanger Drain Lines" The drain lines were removed to facilitate maintenance activities -

regenerative heat exchanger gasket replacemen *

MR-87-0103, " Residual Heat Removal / Reactor Core Isbation Cooling Steam Line Flow Instrumentation"

MR-86-1159, " Mainstream Isolation Valve (MSIV) Positive Leakage Control Systems" The inspector noted that the MR was processed to document the plant as-built condition *

MR-85-0168, " Emergency Diesel Generator Fuel Oil Storage Tank Detector - High Level Alarm" MR-85-0041, " Alternate Rod Insertion (ARI) System" This change provided an additional system (nonsafety-related) to vent the normal reacto.r scram air header pressure independent of the reactor protection system. The ARI was provided to reduce the probability of an anticipated transient without shutdown (ATWS)

even * MR 85-0042, "ATWS-Recirculation Pumps Trip (RPT)"

This modification provided a logic change to reduce the probability of an inadvertent plant trip resulting f rom the RPT syste The review of the selected facility changes revealed that the modifications were processed in accordance with the licensee QA Program and appeared to be acceptable. Questions regarding the design process were discussed with licensee representatives and answered satisfactorily. The NRC inspector had no further questions regarding this are l I

No violations or deviations were identified in the review of this program l l are . Nonlicensed Staff Training (41400)

l l The NRC inspectcr reviewed the licensee's training program, considering .

USAR 17.2.2.4, Training and Indoctrination; USAR 13.2, Training; and l Technical Specification 6.3, Unit Staff Qualification. Selected maintenance training program procedures, records, and licensee events i

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reports-(LERs) were reviewed to evaluate the training program provisions-and any modifications made to the training program associated'with the events. The training of. instrument and control (I&C) technicians was selected for this inspection. Documents reviewed are listed in the attachmen a 3.1 Maintenance Training Program Procedures'

The NRC inspector reviewed selected portions of licensee procedures regarding employee classification, on-the-job (0JT) training, .. student and program evaluations, and specific training and qualification requirement Administrative Procedure ADM-0007 addressed the selection, training, qualification of plant staff personnel; Procedure MSP-0009 addressed the qualification of maintenance personnel, accomplishment of training and OJT, work assignment, and coordination of training activitie Sections 5.1 and 5.2 of MSP-0009 addressed the Technical Specification and plant specific equipment qualification training of maintenance personnel, including supervisors, foremen, and planners. The procedure' required a training matrix to be prepared for each person in the maintenance j department and for this matrix to be utilized by the foremen for the assignment of work activitie The minimum training to be completed by a person assigned as an I&C technician were not clearly specified in the procedure.- The procedural requirements for each person in the I&C department were provided in a training matrix. Examinations and evaluations were required.. Neither Procedure MSP-0009 nor the trainin specified discipline / group (Attachments 2 through 4) g matrix included the specific for the time requirements for. completion of the activities. Interviews and records review revealed.that the I&C technicians were to complete the training necessary to perform a selected activity. 'A review by the NRC inspector of the training matrix for the 180 technicians disclosed that the initial procedure training (Item 6) had not been completed for a number of technicians who were performing routine maintenance activities.

i- This item was discussed with the licensee fur consideration.

3.2 Training Records g The training records, including certifications, for four I&C technicians l were reviewed. The records appeared to be complete with the noted exception of the incomplete initial procedure training for the four I&C technician The initial procedure training was noted to be part of site orientation, but no specified time for completion of the orientation was noted. The item was brought to the attention of the licensee representative for action. The NRC inspector had no further questions regarding this matter.

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The NRC inspector selected three events reported during 1988 for revie The events occurred as a result of errors made by I&C technician . LER 88-004, " Reactor Core Isolation Cooling System Isolation - Inadvertent Shorting of Leads and Procedural Error" (February 2, 1988)- <

The NRC inspector reviewed the condition report (CR 88-0111)

initiated by the licensee on February 2, 1988. As a result of the errors (inadvertent shorting of leads and procedure errors), the licensee reviewed all similar procedures and provided instructions and required reading assignments to the appropriate I&C technicians and foremen. Attention to detail, field inspections of changes, and independent verification of correct locations for any jumper / lifted leads were addressed. The licensee noted that a similar event (LER 87-002) had occurred previously; however, the corrective actions for this event did not reference any evaluations of the need to revise / upgrade the general training or retraining programs for procedure writers or technician . LER 88-016, " Reactor Water Cleanup System Isolation Due to Surveillance Test Procedure Steps not Performed in Sequence" (August 15,1988)

The NRC inspector reviewed the CR No. 88-0645 initiated by the licensee on August 15, 1988. As a result of the failure to follow the procedure, the licensee provided personnel counseling, required reading, and training to the I&C technicians to re-enforce the necessity of following procedures. The licensee noted that similar events had occurred at least four times previously; however, the corrective actions for this event did not reference the previous events nor the evaluations of the need to revise / upgrade the general training or retraining program regarding procedure adherenc . LER 88-019, " Fuel Building Charcoal Filtration System Initiation Due to Lif ting the Wrong Lead" (August 27,1988)

The NRC inspector reviewed the CR 88-0673 initiated by the licensee on August 27, 1988. The licensee provided procedure / shop training to the I&C technicians regarding activities of this type. Additionally, the radiation monitor cabinets and field leads which were routinely lifted and could cause an actuation of ESF were identified locally (colored electrical tape on leads) and in the associated procedure The licensee reported that similar events had occurred at least four times in the past; however, the corrective actions did not reference the previous events, not the evaluation of the need to revise / upgrade

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the general training or retraining programs regarding the control of lifting lead _ --_

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The review of the selceted LERs by the NRC inspector revealed that the training provided I&C personnel for the specific event appeared to.b acceptable; however, the training program effectiveness to prevent

. recurrence could have been enhanced by considering the need to revise / upgrade the training program based on repetitive _ events. .The NRC inspector has no further questions regarding this matte .4 p dit - Surveillance Activities The NRC inspector reviewed a recent QA audit of the performance, 1 training, and qualification of unit staff and a special QA surveillance of maintenance trainin . The QA audit (89-01-I-PTQL/TRNG), conducted on January 10-20,1989, )

reviewed nonlicensed maintenance training and operations personnel 'i training and qualifications, including I&C personnel. A number of findings were identified and corrective actions taken ar.d/or planned i to correct the deficiencies. No specific findings were noted related

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to the I&C grou . ~The special QA surveillance (05-89-03-09), dated March 31, 1989, conducted by the licensee as a result of an 'INP0 letter _ to GSU, 'l requested a review of the maintenance training programs with respect to four program weaknesses identified by recent INPO team visits to j other nuclear sites. The surveillance (short-term review).was  !

performed as the first of two phases of review of-the maintenance training programs'. Interviews revealed that the comprehensive audit- I of the maintenance training programs had just been started at the time of the NRC inspectio The surveillance addressed craftsperson assignment, continuing training, on-the-job training and qualifications, and maintenance management / supervisor involvertent. No specific concerns were identified by the licensee during the surveillanc .5 Conclusions The review and evaluation of the nonlicensed personnel training program and implementation of the program by the NRC inspector revealed that the program and implementation appeared to be satisfactory. However, the training program could be further enhanced by establishing specific ,

acceptance criteria for individual trainire r ased on specific requirements such as those contained in the QA program, iM administrative and department procedures INP0 guidelines (tusk analyses), and other requirements. Goals and milestones for accomplishing the training and retraining plans for each individual should be. considered. This program should provide assurance that each individual worker associated with RBS received a minimum specified initial RBS indoctrination, initial training, and continuirg/ refresher training as specified in the QA program and as directed by licensee management in a timely manne I

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' The review by the NRC inspector of selected LERs,'CRs.'and associated documentation revealed that corrective actions associated with the events reported in these documents appeared to be limited.to required reading and personnel counseling. The evaluations for the need to revise / upgrade the training and/or retraining programs.to sensitize the plant workers .to the <

types of problems being encountered and to prevent recurrence was not .

^f apparent. These two areas were discussed with the license No. violations or deviations were identified in the review of this program

r , . are ' Exit Interview

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The NRC inspector summarized ~the inspection scope and. findings with'

individuals identified in paragraph 1. No information reviewed by the NRC inspector was identified by the licensee as proprietar .

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. ATTACHMENT

Documents Reviewed IMP-6-004, "On-The-Job Training, Experience Gained," . Revision 3 x IMP-6-005, " Student Evaluation," Revision 3 IMP-6-006, " Program Evaluation," Revision 2

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Employee Classification Standards - GSU, Nos. 176, 177, 178, and 179 (Instrument'and Control)

IMP-7-012. "Nonlicensed' Operator Training," Revision 2 IMP.-7-013. " Mechanical Maintenance Training," Revision 2

. IMP-7-014. " Electrical Maintenance Training," Revision 2 IMP-7-015. " Instrument and Control Maintenance Training," Revision 2 ADM-0007, " Selection Training, Qualification, and Evaluation of Plant Staff Personnel," Revision 4 MSP-0009, " Qualification of Maintenance Personnel," Revision 9

~QA~ Audit 89-01-1-PTQL/TRNG, " Performance, Training, and Qualification of Unit Staff" (January 10-20,1989)-

QA Surveillance Report QS-89-03-09, " Maintenance Training Review " March 31, 1989 Gulf States Utilities Annual Report (March 1.- 1987, through March 1, 1988),

dated August 29, 1988 RBNP-010. " Design and Modification Control," Revision 3 ENG-3-006 " River Bend Station Design and Modification Request Control Plan,"

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