ML16245A396
| ML16245A396 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/10/1979 |
| From: | Hardin A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML16245A397 | List: |
| References | |
| REF-SSINS-50-269, REF-SSINS-50-270, REF-SSINS-50-287 NUDOCS 7907060448 | |
| Download: ML16245A396 (3) | |
Text
REGION II J4 101 MARIETTA STREET, N.W.
ATLANTA, GEORGIA 30303 MAY 1 0 1979 SSINS 50-269 50-270 50-287 MEMORANDUM TO:
Files THRU:
R. C. Lewis, Acting Chief, Reactor Operations and Nuclear Support Branch, Region II S. Cantrell, Acting Chief, Reactor Projects Section No.
2, Reactor Operations and Nuclear Support Branch, Region II
.i FROM:
A. K. Hardin, Reactor Inspector, Reactor Projects Section No. 2, Reactor Operations and Nuclear Support Branch
SUBJECT:
TRIP REPORT OCONEE 1, 2, and 3 -
DUKE POWER COMPANY During the period May 3, 1979 through May 7, 1979, I was assigned to perform inspections on each shift at Oconee 1, 2, and 3. In addition, during that period Oconee was to conduct a test of the stability of a modified emergency feedwater system which was to be observed by the inspector, and Nuclear Assurance Corporation (NAC) personnel were to make measurements of the NAC-1.fuel shipping cask.
The measurements were to be observed by the inspector.
- 1.
-INSPECTION Oconee 1 and 2 operated in a normally expected manner at or close to 100 percent power until the plants were reduced to 15% power in preparation for the Emergency Feedwater Flow Test conducted on May 7, 1979.
Unit 3 was on Cold Shutdown preparing to refuel.
An inspection was conducted on each shift and consisted of reviewing logs, instrument readings, observation of equipment and discussions with personnel.
No deviations or noncompliance was observed.
- 2.
EMERGENCY FEEDWATER TEST The licensee was required to modify and test the ability of the emergency feedwater pumps to start automatically and provide adequate feedwater to Units 1 and 2 and determine feedwater stability under different conditions.
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2 Files MAY 1 0 1979 Test No. TT/O/A/325/01 was conducted on the morning of May 7, 1979.
The test went smoothly and acceptance criteria of Section 11.0, 11.1 and 11.2 of the procedure was met. Particular attention was given to observation of operator performance during the test.
Operators were able to control flow perturbations on the system without significant difficulty. Process parameters such as steam generator levels, reactor coolant temperatures, and pressurizer level-remained within acceptable boundries throughout the test.
- 3. OBSERVATION OF NAC-1 FUEL SHIPMENT CASK MEASUREMENTS On May 6, 1979, the inspector observed personnel from Nuclear Assurance Corporation take certain measurements on the inside diameter of the NAC-1 cask. The general purpose of the measurements was to determine out-of-roundness and bow of the cavity.
Procedure "NFS-4/NAC-1, Cavity Measurements" was used to-make the measurements.
The inspector verified that the procedure was followed.
In addition, the inspector:
- a.
Observed all-measurements on the cavity.
- b.
Observed reproducibility measurements.
- c.
Verified, by spot checking, measurements made on the cavity.
A. K. Hardin, Reactor Inspector Reactor Operations and Nuclear Support Branch k.M
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