IR 05000315/1978035
| ML17317A951 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/08/1979 |
| From: | Daniels F, Little W, Masse R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17317A950 | List: |
| References | |
| 50-315-78-35, 50-316-78-36, NUDOCS 7902260121 | |
| Download: ML17317A951 (7) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-315/78-35.;
50-316/78-36 4 ~
Docket No. 50-315; 50-316 License No.
American Electric Power Service Corporation Indiana and Michigan Power Company 2 Broadway New York, NY 10004 Facility Name:
Donald C.
Cook Nuclear Generating Plant, Units 1 and
Inspection At:
Donald C.
Cook Site, Bridgman, MI Inspection Conducted:
December 11-13, 1978 Inspectors:
.
E.
asse (-
. '.--
s.cz D Approved By:
W. K.
ttle, Chief Nuclear Support Section
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Ins ection Summar Ins ection on December 11-13 1978 (Re ort No. 50-315/78-35 50-316/78-36)
Areas Ins ected:
Routine, unannounced inspection in the areas of onsite and offsite review and audit functions, requalification training, core power distribution limits, thermal power evaluations and target axial flux difference calculations.
The inspection involved 42 inspector-hours by two NRC inspectors.
Results:
No items of noncompliance or deviations were identifie " >dSS;0'>g
DETAILS 1.
Persons Contacted
- D. Shaller, Plant Manager
- B. Svensson, Assistant Plant Manager
- J. Stietzel, Quality Assurance Supervisor
- R. Keith, Operations Supervisor
- R. Lease, Operations Production Supervisor
- E. Abshagen, Senior Quality Assurance Auditor D. Nelson, Training Coordinator V. Vandenburg, Nuclear Engineer
"
- K. Baker, USNRC, Resident Inspector
- Denotes those present at the exit interview.
2.
Onsite and Offsite Review and Audit Functions The inspectors verified that the onsite and offsite committee meetings during the previous year were held at least at the frequency required by the Technical Specifications and that
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quorum requirements were satisfied; that proposed tests and experiments which may affect nuclear safety or whose perfor-mance may constitute an unreviewed safety question as defined in 10 CFR 50. 59 were reviewed as required; that violations of the 'Technical Specifications or rules and regulations were reviewed as required; that proposed changes to the Technical Specifications were reviewed as required.
The inspectors verified that records relating to all audits conducted during the previous year were in accordance with written procedures and checklists; that they were conducted by fully trained per-sonnel not having responsibility in the area audited; that the results of audits were documented and reviewed by appropriate management; that proper followup action was either taken, being initiated or in progress; and that the frequency of audits were in conformance with Technical Specifications.
The inspectors verified that D.
C.
Cook operations have been reviewed to detect potential safety hazards, and that the reportable occurrences have been reviewed and evaluated as required by the Technical Specifications.
No items of noncompliance or deviations were identified.
2.
Re uglification Trainin Pro ram The inspectors verified that an operator requalification training program has been established which includes a preplanned lecture
schedule and method of documenting attendance, and that on-the-job training requirements have been specified which includes control manipulation, discussion/review of changes in facility design, procedures and license, and review of abnormal and emergency pro-cedures.
The inspectors verified that the records of five licensed individuals contained required course and yearly examinations with answers, documentation of manipulations required by Appendix A to
CFR 55 and reqm.red simulations of emergency and abnormal con-ditions, results 6f supervisory evaluations of examinations and manipulations, and documentation verifying that required additional training and individual study has been accomplished.
No items of noncompliance or deviations were identified.
3 ~
Core Power Distribution Limits U
The inspectors verified that the values of hot channel factors cal-culated by the analysis code and recorded were within Technical Specification limits; that axial flux difference limits have been maintained and the logging of applicable penalty deviations were in accordance with Technical Specification requirements; and that quadrant power tilt limits were being observed and were within Technical Specification limits.
No items of noncompliance or deviations were identified.
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Core Thermal Power Evaluation The inspectors verified that initial conditions required in plant procedure, 1-OHP 4030 STP 029,
"Thermal Power Determination,"
were met prior to performing evaluation; the frequency of evalu-ations at least meet Technical Specification requirements and required limit for adjustment was observed.
No items of noncompliance or deviations were identified.
5.
Tar et Axial Flux Difference Calculation The inspectors verified that target flux difference updating has been done with the frequency methodology prescribed by the Technical Specifications, procedure and program; the updating has been trans-mitted and made available to the operators; and operators were meeting the operating limitations based upon the target flux dif-ference.
No items of noncompliance or deviations were identified
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6.
Exit Interview The inspectors met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on December 13, 1978.
The inspectors summarized the scope and findings of the inspection.
It was brought to><he attention of those present that, although all records and documents required for this inspection were made avail-able, in some cases they were not readily available and that more attention or possibly a better method should be developed.