IR 05000316/1978024
| ML17317A698 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/26/1978 |
| From: | Kohler J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17317A697 | List: |
| References | |
| 50-316-78-24, NUDOCS 7810310340 | |
| Download: ML17317A698 (5) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Repor t No. 50-316/78-24 Docket No. 50-316 License No. DPR-74 Licensee:
American Electric Power Service Corporation Indiana and Michigan Power Company 2 Broadway New York, NY 10004 Facility Name:
D.
C.
Cook Nuclear Plant, Unit 2 Inspection At:
D.
C.
Cook Site, Bridgman, MI Inspection Conducted:
August 24 and 25, 1978
~5~~ ye Inspector:
J.
E. Kohler
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Approved By:
J. F. Streeter, Chief Nuclear Support Section
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Ins ection Summar Ins ection on Au ust 24 and
1978 (Re ort No. 50-316/78-24 Areas Ins ected:
Routine, announced inspection of Unit 2 preoperational tests involving the initial rise to 70% and 100% power.
The inspection involved 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of onsite time by one NRC,inspector.
Results:
Of the areas inspected, no items of noncompliance or deviations were identifie DETAILS Persons Contacted D. Shaller, Plant Manager V. Vanderburg, Chief Nuclear Engineer T. Allen, Nuclear Engineer E. Smarella, Technical Supervisor 2 ~
Unit 2 Moderator Tem erature Coefficient The inspector reviewed the results of physics testing performed at approximately 70% and 100% power to determine the moderator tempera-ture coefficient.
The test was performed by maintaining the reactor at a constant power level while initiating a cool down and subsequent heat up.
Power was maintained constant through control rod action.
Results showed the coefficient to be negative and within the Techni-cal Specif)cation limit of less than zero and greater than-3.9 x 10 K/K/ F.
Reactivity was measured using a reactivity computer.
The inspector has no further questions regarding this item.
uadrant Power Tilt Results of incore analysis were examined on Unit 2 to determine whether tilting in excess of the 1.02 technical specification was being experienced.
Records reviewed showed no tilting either with incore or excore instrumentation.
The inspector has no further questions regarding this item.
4, Axial Flux Difference The inspector reviewed surveillance records of the axial flux distri-bution in order to determine whether the plant was being operated within the target band.
It was determined that the delta flux limits were being updated periodically and no axial offset in excess of the target band was observed.
The inspector has no further questions regarding this item.
5.
Power Plateau Review The inspector reviewed the results of physics testing performed at approximately 70% and 100%,power to confirm the design power char-acteristics.
The licensee performed the following checks during the hold perio Radiation protection survey Radiochemical analysis of reactor coolant Vibration and NIS data accumulation The inspector has no further questions regarding this item.
Power Distribution Review The inspector reviewed the full core flux maps taken at 70% and 100% power and determined that the nuclear hot channel factors and quadrant power tilt were within Technical Specification limits.
The inspector has no further questions regarding this matter.
Exit Interview At'he conclusion of the inspection, the inspectors met with Hr.
Shaller and summarized the results of the inspectio ~
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