IR 05000315/1982023
| ML20028E211 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/05/1983 |
| From: | Farrell R, Hawkins F, Kish J, Peschel J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20028E206 | List: |
| References | |
| 50-315-82-23, 50-316-82-23, NUDOCS 8301210076 | |
| Download: ML20028E211 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-315/82-23(DETP), 50-316/82-23(DETP)
Docket Nos. 50-315, 50-316 Licenses No. DPR-58, DPR-74 Licensee: American Electric Power Service Corporation Indiana and Michigan Electric Company 2 Broadway New York, NY 10004 Facility Name:
D. C. Cook Nuclear Power Plant, Units 1 and 2
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Inspection At:
D. C. Cook Site, Bridgman, MI Inspection Conducted: November 29 through December 3, 1982
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C Inspectors:
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/ M, J50kL M. P schel
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4.IMN l2.!Z ?!8E J. Kish Approved By:
F. C. Hawkins, Chief l/f/63
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Management Programs Section Inspection Summary:
Inspection on November 29 through December 3, 1982 (Reports No. 50-315/82-23(DETP); 50-316/82-23(DETP))
Areas Inspected: Surveillance and calibration program; nonroutine reporting; licensed requalification training; licensed and nonlicensed training; and previously identified inspection findings. The inspection involved a total of 80 onsite inspector-hours by three NRC inspectors.
Results: No items of noncompliance or deviations were identified.
8301210076 830107 PDR ADOCK 05000315 G
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DETAILS Persons Contacted Indiana and Michigan Electric Company
- W.
Smith, Jr., Plant Manager
- E. Townley, Assistant Plant Manager
- B.
Svensson, Assistant Plant Manager
- A. Blind, Performance Supervising Engineer (Technical Department)
- J. Spietzel, QA Supervisor
- L. Matthias, Administrative Supervisor
- D.
Nelson, Training Coordinator T. Stephens, Senior Performance Engineer (Operations)
K. Baker, Operations Superintendent D. Duncan, Controls and Instrumentation Supervisor R. Dudding, Maintenance Supervisor D. Wizner, Maintenance QC Supervisor D. Krause, Operations QC M. Brown, Training Instructor W. Nichols, Training Instructor P. Craig, Training Instructor NRC
- E.
Swanson, Senior Resident Inspector
- N. DuBry, Resident Inspector
- Denotes persons attending exit meeting on December 3, 1982.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (315/81-17-01 and 316/81-20-01): Failure of licensed operators to complete reviews of design, license, and facility changes as re-quired by 10 CFR 55, Appendix A.
The inspectors reviewed records and flies of the licensed operators review of design, license, and facility changes. Based upon the increased emphasis placed upon ensuring that the licensed operators were reviewing the changes and the Training Coordinators determination that this would continue, this item is considered closed.
Functional or Program Areas Inspected The details of areas inspected are contained in Sections I, II and III of this report.
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i SECTION I Prepared By:
R. E. Farrell
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Reviewed By:
F. C. Hawkins, Chief Management Programs Section l '.
Surveillance Testing Program a.
The surveillance testing program was reviewed to verify that a.
master schedule for surveillance testing, calibration, and inservice inspections required by ANSI 18.7 - 1972 was established.
Procedure PMI-4030, Revision 7, " Surveillance Testing," was reviewed.
This procedure assigns required surveillances to specific departments and constitutes a Master Surveillance List. Each department
individually maintains a list reflecting the frequency and status of
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each test, calibration, and inspection.
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b.
A central computerized Master Surveillance Schedule has been developed to minimize manual control of surveillances and ease the administrative burden on department heads. This schedule has been only partially implemented and is in the process of final review
and correction.
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Procedure PMI-4030, Revision 7, " Surveillance Testing," included c.
assignment of responsability to the Plant Manager or his assistant for maintaining the list up to date, d.
Tests, calibrations, and inspections are required to be done in accordance with approved procedures which include acceptance criteria.
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Several levels of management are assigned responsibility for reviewing and evaluating test data.
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Each department head is responsible for assuring timely completion of I
his department's assigned tests, calibrations, and inspections.
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No items of noncompliance were identified.
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2.
Calibration Program
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a.
The inspector interviewed the Controls and Instrumentation (C&I)
Supervisor regarding calibration of components which were not
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. identified in the technical specifications. The-C&I Supervisor maintains a list of all instruments in the plant reflecting
calibration requirements and status. Calibration is done by (
approved procedures which include acceptance criteria.
b.
The C&I Supervisor or his assistant reviews calibration results for acceptability.
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No items of noncompliance were identified.
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Observation of Surveillance Testing and Calibration a.
The inspectors observed plant personnel weighing ice baskets in the ice condenser portion of the containment.. Calibration blocks (reference weights) are used before and after weighing to check the calibration of the scales used. The crew observed was utilizing check lists and data sheets.
Scale calibration was checked in the ice condenser at the same temperature at which the scale was used for the surveillance.
b.
The inspectors conducted a walk-through of the plant randomly checking the calibration status of instruments. Calibration status stickers were inplace.
No items of noncompliance were identified.
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Nonroutine Reporting Program a.
The inspector reviewed the following procedures for compliance with 10 CFR 50.55(e), 10 CFR 21, and the technical specifications:
PMI-2210, Revision 3 (8-28-79) " Plant Reporting" PMI-7030, Revision 6 (10-12-82) " Condition Reports" PMI-7070, Revision 0 (1-6-78) " Defect and Noncompliance Reporting" PMI-7080, Revision 0 (10/12/82) " Control of NRC Documents and Committments" b.
The inspector interviewed the Operations Superintendent regarding implementation of the procedures.
No items of noncompliance were identified.
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Vendor Bulletins and Circulars The inspector reviewed the following procedures to verify compliance with Criterion VI of 10 CFR 50, Appendix B:
PMI-4060, Revision 3 (2-23-82) " Technical Data Books" PMI-2030, Revision 3 (6-30-81) " Control of Information Resources (Document Control)"
No items of noncompliance were identified.
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SECTION II Prepared By:
J. M. Peschel Reviewed By:
F. C. Hawkins, Chief Management Programs Section Nonlicensed Training A review was conducted of the overall training and retraining activities for nonlicensed employees, and general training for licensed employees to ascertain that the training program is in conformance with Technical Specifications, the Final Safety Analysis Report, and Quality Assurance Program requirements. TWo inspectors attended the December 1, 1982, Nuclear General Employee Training Program training session. Twenty-seven training records were reviewed to ascertain if the licensee's training procedures were followed.
Interviews were conducted with selected licensee and con-tractor personnel to evaluate the adequacy of training. The following documentation was reviewed to ascertain if applicable requirements were included:
Plant Manager Instruction, PMI-2070, Revision 6, Training Maintenance Head Instruction, MHI-2070, Revision 5, Training Operations Head Instruction, OHI-2070, Revision 2, TP-3, Training Administrative Head Instruction, AHI-2070, Revision 4, Training Quality Head Instruction, QHI-2070, Revision 1, TP-4, Training Technical Head Instruction, THI-2070, Revision 6, TP-1, Training Quality Head Instruction, QHI-7021, Revision 0, Qualification of Plant Quality Assurance Audit Personnel AEPSC Procedure No. I-21, Revision 0, Auditor Qualification Case Nuclear Procedure N.Al-3, Revision 0, Auditors - Qualification, Training, and Certification Nuclear General Employee Training Program, Revision 2 Shift Technical Advisor Program, Revision 1 Shift Technical Advisor Requalification Training, Revision 1 Final Safety Analysis Report, July 1982, Section 12 AEPSC General Procedure No. 2.0, Revision 0, Quality Assurance Program AEPSC General Procedure No. 2.1, Revision 1, Quality Assurance Program for the Donald C. Cook Nuclear Plant Nuclear Safety and Design Reveiw Committee:
(NSDRC) Audit No. 86, (NSDRC) Audit No. 74 (NSDRC) Audit No. 64 (NSDRC) Audit No. 51 Technical Specifications As a result of an audit recommendation in NSDRC Audit No. 40, a systems training program was established for Maintenance Department personnel. This program is identified in MHI 2070, " Training." The audit findings of NSDRC Audit No. 74 states that the intended purpose of the training is to provide all main-tenance men with enough knowledge of the plant systems so they would be able to check their clearances before starting work and know that they were properly protected. The program was begun in September 1979, but the training has not been conducted on a continuous basis due to outages, shortages of personnel in
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the Maintenance and Training Departments, and a lack of awarene=s by key staff personnel of the prescribed corrective action concerning the audit recommenda-tion. Discussions with licensee management revealed that the training program problems have been resolved and that approximately two weeks after the completion of the present Unit 2 outage, the systems training program will be
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.during non-outage periods, and will meet the requirements of MHI-2070. The reinitiated. This training program will be conducted as schedules permit i
- reinitiation of Plant System Training for the Maintenance Department is
considered an open item (50-315/82-23-01; 50-316/82-23-01).
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SECTION III Prepared By:
J. N. Kish Reviewed By:
F. C. Hawkins, Chief Management Programs Section Operator Requalification Training Program A review of the Operator Requalification Training Program was performed to ensure the program met U.S. NRC regulations and that the regulations were being properly implemented. Specifically, the Final Safety Analysis Report was reviewed to ensure that the committments were consistent with the requirements of 10 CFR 55, Appendix A and NUREG-0737. The latest revision of the Operator Requalification Training Program was also reviewed to ensure consistency between it and the FSAR.
Included in this review was attendance by an inspector at a non-licensed replacement operator program training'
session (to determine the quality of the lecture material and attention given to the lecturer) and reviewing and analyzing two randomly picked licensed operators files (to determine if the required documentation was indeed present). An interview was also conducted with a randomly picked licensed operator in addition to interviewing and questioning of several training instructors.
In addition the following documents were reviewed:
D. C. Cook - Final Safety Analysis Report, Section 12.2 Licensed Operator Requalification Program.
D. C. Cook Nuclear Plant, Licensed Operator Requalification Program - July 1982.
D. C. Cook Nuclear Plant, Licensed Operator Requalification Program - July 1980.
D. C. Cook Nuclear Plant, Operator Replacement Training - May 1982.
Post TMI_ Requirements set forth a set of prerequisites to be used in re-qualifying licensed operators. These requirements are specified in NUREG-0737.
Included in NUREG-0737 is a letter from Mr. Harold Denton on March 28, 1980, that specifically addresses and describes the section on Requalifying licensed operators.
As a result of this letter, D. C. Cook has revised their Licensed Operator Requalification Training Program. The most recent program commits to con-ducting lectures with an emphasis on identified weak areas based as past examination results. Currently, there is no formal documentation or verification that this is being done. Although the Training Coordinator and a Training Instructor explained that it is being accomplished, there is no supporting documentation. The licensee committed to documenting this process. The development of a process to document that identified weak areas are emphasized.during licensed operator training is considered an open item (50-315/82-23-02; 50-316/82-23-02).
Exit Interview The inspectors met with licensee representatives denoted in the Persons Contacted paragraph at the conclusion of the inspection on December 3, 1982.
The inspectors summarized the purpose and scope of the inspection and the findings.
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