IR 05000369/1982016
| ML20058C176 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/25/1982 |
| From: | Burnett P, Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058C150 | List: |
| References | |
| 50-369-82-16, 50-370-82-11, NUDOCS 8207260285 | |
| Download: ML20058C176 (4) | |
Text
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Report Nos. 50-369/82-16 and 50-370/82-11 Licensee:
Duke Power Company P. O. Box 2178 Charlotte, NC 28242 Facility Name: McGuire 1 and 2 Docket Nos. 50-369 and 50-370 License Nos. NPF-9 and CPPR-84 Inspection at McGuire site on Lake Norman, North Carolina Inspector:
JgggF 6-24;72 P.
Burnett Date Signed Accompanying Personnel:
Maw-Sherng NI, Taiwann AEC (May 11-14)
Hon-Wei Syh, Taiwan AEC (May 11-14)
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U Approved by: _..F. Jape, Section ieff Date Signed c
Engineering Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on May 11-14 and June 9-11, 1982 Areas Inspected This routine, announced inspection involved 46 inspector-hours on site in the areas of review of preoperational test procedures, followup of licensee event reports and followup of inspector identified items.
Results No violations or deviations were identified.
8207260285 820628 PDR ADOCK 05000369 G
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- M. D. McIntosh, Station Manager W. M. Sample, Project and Licensing Engineer T. C. McConnel, Superintendent of Technical Services D. Rains, Superintendent of Maintenance
- E. E. Estep, Projects Engineer
- 0. B. Lampke, Licensing Engineer D. Marquis, Reactor Engineer B. H. Hamilton, Performance Engineer G. Gilbert, Operations Engineer M. E. Pacetti, Station Safety Review Group M. W. Neill, Station Safety Review Group G. I C. Cruzan, Station Safety Review Group Other licensee employees contacted included two operators and two office personnel.
NRC Resident Inspectors P. R. Bemis, Senior Resident Inspector P. C. Hopkins, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 11, 1982, with those persons indicated in paragraph 1 above. Licensee management confirmed the two commitments addressed in paragraph 6.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Preoperational Test Procedures - Unit 2 The inspector reviewed changes made to two test procedures:
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TP/2/A/1200/02, NI Accumulator Functional Test (five changes) and
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TP/2/A/1200/04, Containment Spray System Functional Test (seven changes).
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All changes were properly reviewed and justified.
j The draft and approved version of OP/2/A/6100/11, Reactor Coolant System l
Initial Fill and Vent and Hydrostatic Test, were reviewed and compared.
From the changes and additions made to the draf t to produce the approved version it was concluded that an adequate technical review of the draft had
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been performed.
6.
Licensee Event Report (LER) Followup
The LERs referenced below were reviewed to assure the accuracy and
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completeness of the reports, that regulatory requirements had been met, and
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that the stated and appropriate corrective actions had been taken.
l R0-369/82-10, Continuing Failure of Digital Rod Position Indication
The report stated that all digit.11 rod position indication for rod K-8 had
been lost on January 20, 1982 and that the condition persisted until repairs
were effected on January 25, 1982.
The inspector reviewed the licensee's i
internal incident investigation report number 82-12, the Unit 1 shift supervisor's log book for the period January 20 to February 5, 1982, the
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station modification package NSM MG-0624, Change CRDM Cables and Connectors
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Around Platform, and work request number 91691.
From this review it was determined that the repair was not ef fected until February 5,1982.
The required surveillance of rod position using the flux mapping system was continued until the unit was shutdown to permit repair.
It was concluded that except for the administrative error of reporting the wrong date the report was factual and the corrective action satisfactory. At the exit interview the licensee made a commitment to issue a corrected LER by
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June 30, 1982.
The action will be tracked as inspector followup item
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50-369/82-16-01, correct R0-369/82-10.
R0-369/82-23 Reactor Coolant System Approached Shutdown Margin The report stated that on March 12, 1982 the reactor coolant system (RCS)
boron concentration had been diluted during filling and venting operations
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by the addition of water at an unknown boron concentration.
Beyond the
immediate corrective action of adding boric acid to the RCS the licensee j
stated that procedural changes would be made to require verification of blender output.
The inspector reviewed incident investigation report number 82-27, which was initiated on March 13, 1982 and reviewed and approved on April 2, 1982.
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Also reviewed were the shif t supervisors logbook for March 12, 1982, and OP/1/A/6150/01, Filling and Venting the Reactor Coolant System, which incorporated changes through number 27 approved on April 21, 1982.
This review confirmed that the event occurred as described and that appropriate corrective action had been proposed in a timely manner.
However, that corrective action, the addition of a cautionary note after step 3.2.6 of OP/1/A/6150/01, had yet to be implemented at the close of this inspection.
From discussions with plant personnel it was determined that other extensive
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changes, not related to this event, had been proposed for OP/1/A/6150/01.
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Approval of the entire package of changes had Deen delayed pending revision of Station Directive 3.1.2.8, Operations Handling of Procedures.
This issue was discussed at the exit interview.
Licensee management stated that the corrective action change to OP/1/A/6150/01 could have and should have been handled more expeditiously under existing plant procedures.
Management further stated that an improved method of tracking and implementing commitments to the NRC and corrective actions identified in incident investigation reports would be instituted. This commitment will be tracked as inspector followup item 50-369/82-16-02, corrective action tracking system.
7.
Other Activities During the first period of this inspection, the inspector in the company of the resident inspectors and two inspectors from the Taiwan AEC made extensive tours of the Unit 2 containment building, Unit 2 areas of the auxiliary building and the shared Units 1 and 2 control room.
During the second period of the inspection, the inspector assisted the resident inspector in inspection activities related to the inoperability of seismic restraints for the Unit I residual-heat-removal heat exchangers.
That activity will be addressed in the resident inspector's report for June 1982.
8.
Inspector Followup Item (Closed) Inspector Followup Item (50-369/82-01-02): Evaluation of Nuclear Instrument Sensitivity in the Below-The-Bank Rod Test.
The licensee has submitted additions (four graphs) to the startup test report that demonstrate the response of the excore power-range nuclear instruments to the below-bank rod as a function of rod position. In addition the inspector has reviewed and discussed the results on incore flux maps and axial power traces obtained during the test. These results confirm that a mispositioned rod is detectable and locatable.