IR 05000369/1981031
| ML20040E680 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/06/1982 |
| From: | Burnett P, Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20040E670 | List: |
| References | |
| 50-369-81-31, 50-370-81-20, NUDOCS 8202050237 | |
| Download: ML20040E680 (4) | |
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UNITED STATES d
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NUCLEAR REGULATORY COMfilSSION c,
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REGION 11 e
101 MARIETTA ST., N.W., SUITE 3100
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Report Nos. 50-369/81-31 and 50-370/81-20 Licensee:
Duke Power Company P. O Box 2178 Charlotte, North Carolina 28424 Facility Name:
McGuire 1 and 2 Docket Nos. 50-369 and 50-370 License Nos. NPF-9 and CPPR-84 Inspection at McGuire si e on Lake Norman, North Carolina Inspector:
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urnet Date Signed A g44
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e Approved by:
F. Jape, SectioTn'Clifef Dat'e Sisned Engineering Inspection anc Engineering and Technical Inspection Division SUMMARY Inspection on December 15-18, 1981 Areas Inspected This routine, unannounced inspection involved 28 inspector-hours on site in the areas of surveillance test witnessing and startup program results review.
Results No items of noncompliance or deviation were identified.
8202050237 820108 PDR ADOCK 05000370 Q
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REPORT DETAILS 1.
Persons Contacted Licensee Employees M. D. McIntosh, Plant Manager
- W. M. Sample, Projects and Licensing Engineer B. Hamilton, Performance Engineer T. Pedersen, Test Engineer D. Marquis, Reactor Engineer T. Parker, Training Other licensee employees contacted included several engineers and reactor operators.
NRC Resident Inspector P. R. Bemis
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on December 18, 1981 with Mr. M. D. Sample.
The commitments discussed in~ paragraph 5 were recon-firmed.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Surveillance Testing of Complex Systems (61701)
In accordance with portions of technical specifications 4.1, 4.3, 4.5, 4.6, 4.7 and 4.8, periodic test PT/1/A/4200/09A, " Engineered Safety. Features -
Actuation," is performed every eighteen months. In general terms the test I
must demonstrate the capability of the diesel generators, following extended
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operation to restart and load in response to manually initiated safety i
injection and phase A and phase B isolation signals. In another part of the i
test, with offsite power available, the test must demonstrate load sequenced to the offsite power supply. The third section demonstrates diesel gener-ator performance during a station blackout. In all parts of the test the l.
proper and timely movement of valves and starting of motors is compared with j
specific technical specification requirements.
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The tests-were performed separately on trains A and 8 of engineered safety features equipment.
The inspector chose to witness the train B tests. In preparation for that activity the test procedure was reviewed and some of the licensee's preparatory activities observed.
During testing of the manual ESF actuation buttons it was observed on several occassions that not all of the contacts of the push buttons made up.
Hence not all safety features were initiated every time the buttons were pushed.
In response to these problems the licensee committed to the following actions:
a.
After completion of testing and before startup the three unreliable switches will be replaced with new, tested switches.
b.
The switches will be further tested after installation to assure proper wiring continuity.
c.
The manufacturer will conduct an inspection and evaluation of the switches and issue a report in January,1982.
d.
Corrective action based upon the manufacturer's recommendations will be accomplished during the scheduled outage in March,1982.
e.
The reactor operators will be trained by reviewing the problems encountered. The techniques found to best ensure contact makeup will be described and the need to confirm equipment start emphasized.
The commitments will be tracked as inspector-followup item 50-369/81-31-01.
The briefing of the craftsmen, auxiliary operators and reactor operators taking part in the train 8 test began approximately two and one-half hours before test initiation and lasted for about one hour.
The inspector attended the briefing and found it adequate.
The test which began at 0342 on December 18, 1981, was witnessed in the
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control room. The one problem observed from that vantage point was that the manual ESF reset switches, the same kind of push button switches addressed earlier in this section failed to make up all contacts on one occasion.
Subsequently the licensee broadened the commitments above to include the reset buttons.
Persons taking data and making observations throughout the plant did not identify any major problems such as failure of motors to start or valves to move.
Review of the observations to assure that all valves moved with the proper speed was not complete at the end of the inspection.
6.
Startup Program Results Review
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a.
Core Power Distribution (61702)
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The licensee used a computer program SNA CODE to convert flux distri-butions obtained using movable incore detectors to power distributions
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and to then calculate the parameter's FQN, FXY, FAH and R1 addressed in j
technical specifications 3.2.2 and 3.2.3.
The input and output of SNA
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CODE are similar to INCORE, the program usually used with Westinghouse reactors. Whether calculational methods are similar was not deter-mined.
Review of one flux map obtained at 75'; power and two obtained at 30*;
power for two different control rod configuations indicated acceptable power distributions.
7.
Power Coefficient (61709)
Test procedures titled " Doppler Only Power Coefficient Verification" were performed at 30, 50 and 75*4 power using procedures numbered TP/1/A/2150/04A, TP/1/A/2150/048 and TP/1/A/2150/04C respectively. Review of the completed procedures showed that all had been performed in their entirety and all necessary data obtained. Spot checking of some of the internal calculations did not reveal any errors.
8.
Miscellaneous Activities The inspector completed the test and other required activities and obtained the security badge necessary to have unfettered access to the operating unit.
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