IR 05000424/1987054
| ML20235H536 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/22/1987 |
| From: | Burnett P, Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20235H529 | List: |
| References | |
| 50-424-87-54, NUDOCS 8710010095 | |
| Download: ML20235H536 (6) | |
Text
1 UNITED STATES pm REC (q#'o NUCLEAR REGULATORY COMMISSION g
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Report No.:
50-424/87-54 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket No.:
50-424 License No.: NPF-68 Facility Name:
t'ogtle 1 Inspection Conducted: September 8 - 11, 1987 Incpector:
[Af (hyL 9%
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T.~ Burnetr
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Date Signed Approved by:
b 7!W8 F. Jape. Section Chief 4'
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Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope: This routine, unannounced inspection addressed the areas of review of completed startup tests and startup program status.
Results:
No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- G. Bockhold, Jr., General Manager W. L. Burmeister, On-shif t Operations Supervisor
- C. L. Cross, Senior Regulatory Specialist
- J. F. D'Amico, Nuclear Safety and Compliance Manager R. J. Florian, Reactor Engineering Supervisor W. C. Gabbard, Regulatory Specialist
- C. Garrett, Operations Engineer
- T. Greene, Plant Manager T. S. Hargis, On-shift Operations Supervisor
- W. F. Kitchens, Operations Manager
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- W. E. Mundy, Quality Assurance Supervisor Other licensee employees contacted included engineers, security force members, and office personnel.
Other Organizations W. Pheonix, Consul Tec 0. D. Hayes, Consul Tec NRC Resident Inspectors H. H. Livermore, Senior Resident Inspector, Construction J. F. Rogge, Senior Resident Inspector, Operations R. J. Schepens, Resident Inspector
- C. W. Burger, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 11, 1987 with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection findings.
No dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
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4.
Unresolved Items ho unresolved items were identified during this inspection.
5.
Tests Completed at 75% Power (72616)
a.
1-6SE-02, Incore Detector and Thennocouple Mapping, was completed on May-12 1987. The flux maps obtained included V1-050887-1
through V1-050887-10, which included both full and quarter core maps for the incore-excore correlation as well as for monitoring thermal limits.
The following Technical Specifications were confirmed to be satisfied: 3.2.1 (Axial Power), 3.2.4 (Quadrant Power Tilt Ratio), 3.2.2 (Heat Flux), and 3.2.3 (Hot Channel Factor).
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b.
1-6RJ-01, At Power Intercomparison of Reactor Protection Inputs and Plant Computer Outputs Test, was completed on April 23, 1987.
All acceptance criteria on comparison of readings were satisfied.
c.
1-6SE-01, Axial Flux Difference Calibration, yielded results different from those observed at other, similar facilities. The data points of upper or lower excore neutron chamber current versus incore measured axial offset did not define a straight line as well as did results at other facilities. A typical result, for power range neutron detector N41, is shown in figure 1.
The intersection of the lines is more displaced from zero offset than is usually observed.
The licensee is currently checking records to assure that the chambers are fully inserted in their wells.
The inspector will continue the review and analysis of the 75%
data as well cs those obtained at 100% power during a future inspection.
No violations or deviations were identified.
6.
Tests Completed at 100% Power (72624)
The inspector reviewed the following startup test procedures completed at 100% of rated thermal power (RTP):
a.
1-6SE-02, Incore Detector and Therm 9 couple Mapping, was completed on May 30, 1987.
A single flux map was obtained, V1-0503087-1.
The following Technical Specifications were confirmed to be satisfied: 3.2.1 (Axial Power), 3.2.4 (Quadrant Power Tilt Ratio),
3.2.2 (Heat Flux), and 3.2.3 (Hot Channel Factor).
b.
1-6RJ-01, At Power Intercomparf:on of Reactor Protection Inputs and Plant Computer Outputs Test, was completed on June 1, 1987.
All acceptance criteria on comparison of readings were satisfied.
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c.
1-6SC-01, Power Coefficient Determination, was completed on i
June-1, 1987.
Eight observations of the measured ratio of change in i
average RCS temperature to change in percent power were obtained, l
They ranged in value from -0.84556 to -1.8501.
The licensee accepted the average result of -1.0155; since it did agree within 0.5 of the predicted ratio of isothermal temperature coefficient l
to power doppler coefficient of 0.868096.
The inspector performed I
a statistical analysis of the eight observations and found that
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the largest magnitude value, -1.8501, differed from the mean by
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more than 2.46 times the sample standard deviation of 0.33S5.
Treating the large magnitude value as an outlier, the seven remaining data were reanalyzed to obtain a mean and standard deviation of -0.8963 and 0.04211 respectively.
This result is much closer to the predicted value with far less uncertainty.
At the exit interview, a procedure or program for establishing bases for rejecting test data was discussed.
d.
1-6AE-02, Calibration of Steam and Feedwater Flow Instrumentation at Power, was completed on July 8,1987.
Following retests, all indicators satisfied the acceptance criteria.
No violations or deviations were identified.
7.
Status of Startup Test Program (72400)
In a letter dated September 4, 1987, the licensee had identified several tests to be performed in conjunction with the start of the early October 1987 outage. During this inspection, the licensee stated that three of the tests would not be performed. They are Load Swing at 100% Power (FSAR 14.2.8.2.27), Large Load Reduction at 100% Power (FSAR 14.2.8.2.52), and Autcmatic Steam Generator Level Control Test at 100%
Power (FSAR 14.2.8.25), which cannot be performed as exhaustively if the first two are not performed.
Additionally, they plan to delete the Steam Generator Moisture Carry-over Test (FSAR 14.2.8.2.54).
The argument against the test is that all other Model F steam generators have shown carryover in the order of 0.01%, well below the warranty value of 0.25%.
Formal justification for deleting these tests from the approved test program has not yet been received for evaluation.
Current planning is to initiate the outage or: October 9, 1987, by performing the loss of 100% electrical load test. Most of the required l
data were cbtained during two actual loss of load events, but the architect-engineer has identified additional dynamic response data that are required to satisfy commitments and code requirement _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _
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8.
Review of Startup Test Report (90713)
The Startup Test Report for activities completed through June 1987 was issued on August 31, 1987, and was available on site for review.
Although the review is not complete, the results so far are that the report accurately describes the tests performed and the results obtained.
Compared with other similar reports, this report is more descriptive of the work performed and contains more detailed descrip-tion of results in both tabular and graphical form that the typical
1 report.
It reflects well on the licensee.
9.
Management Meeting (30702)
A management meeting between corporate officials and NRC management was i
held onsite on September 10, 1987. The inspector attended and partici-
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pated in the meeting. The meeting minutes will be published elsewhere.
Attachment:
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