IR 05000424/1986052
| ML20203C043 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/01/1986 |
| From: | Jape F, Macdonald J, Larry Nicholson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20203C035 | List: |
| References | |
| 50-424-86-52, NUDOCS 8607180345 | |
| Download: ML20203C043 (4) | |
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SR FE4 UNITED STATES NUCLEAR REGULATORY COMMISSION o
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REGION 81
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Report No.:
50-424/86-52 Licensee: Georgia Power Company P. O. Box 4545
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Atlanta, GA 30302
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Docket No.: '50-424 License No.: CPPR-108 Facility Name: Vogtle 1
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Inspection Conducted: June 2-6, 1986 Inspectors:
L. E. N1 olson D1te Signed G
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Macdonal p Date Signed
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// b Approved by:
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Date Signed F. Jape, Sectron Chief f
Division of Reactor Safety SUMMARY-Scope:
This routine, unannounced inspection was in the areas of Module 7 Readiness Review and preoperational test witnessing.
Results: No violations or deviations were identified.
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8607180345 860707
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PDR ADOCK 00000424 G
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REPORT DETAILS
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1.
Persons Contacted Licensee Employees
- R. M. Bellamy, Manager, Test, Outage
- S. A. Bradley, Readiness Review
- P. 0. Foster, Vice-President, Project Support
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- W. C. Gabbard, Regulatory Specialist
- E. D. Groover, QA Site Manager (Construction)
- W. C. Ramsey, Readiness Review Manager
- H. P. Walker, Manager, Unit Operations Other licensee employees contacted included engineers, technicians, and operators.
NRC Resident Inspector
- J. F. Rogge, Senior Resident Inspector, Operations
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 6,1986, with those persons indicated in paragraph 1 above. The inspectors described the areas inspected and discussed in detail the inspection findings.
No dissenting comments were received from the licensee. ~ The following new item
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was identified:
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Inspector Followup Item 424/86-52-01, Review Evaluation of ODR T-1-86-1839, (paragraph 5).
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
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Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
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Unresolved Items Unresolved items were not identified during the inspection.
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Preoperational Test Witnessing (70433)
The inspectors observed dynamic adjustment of the process controllers in the chemical and volume control system (CVCS) per maintenance procedure 23832-C and test procedure 1-38G-04, Boric Acid Blender Preoperational Test. The procedures were reviewed and testing was observed to determine that NRC requirements such as contained in Regulatory Guide 1.68 and the Final Safety Analysis Report were being met. The following attributes were verified in this review:
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Maintenance and testing were performed in accordance with approved procedures.
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Latest revisions of the approved test procedures were available and in use by personnel performing the tests.
Test equipment required by the procedures was calibrated and installed.
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Test data were properly collected and recorded.
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Adequate coordination existed among personnel involved in the test.
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Test prerequisites were met.
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Temporary modifications such as jumpers were installed and tracked in
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accordance with administrative controls.
Problems encountered during testing were properly documented.
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The inspectors observed a problem with the operation of the boric acid blender selector switch causing improper valve actuation and the loss of all off-site power.
Initial licensee evaluation indicated an incorrect jumper permanently installed by the vendor'in the CVCS. This event was documented on Operations Deficiency Report (ODR) T-1-86-1839.
Final review of the evaluation will be tracked as Inspector Followup Item (IFI), 424/86-52-01:
Review Evaluation of ODR T-1-86-1839.
No violations or deviations were identified in the areas inspected.
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Reactor Coolant System Hydrostatic Test Results Review (70562)
Tha inspectors reviewed the completed data package for reactor coolant system (RCS) cold hydrostatic test (TP 1-300-03).
The data package was reviewed to verify the following:
Test changes were made in accordance with the licensee's administrative
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controls.
Changes made to the procedure did not alter the intent of the test.
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Water quality was maintained in accordance with the requirements
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specified.
The hydrostatic test pressure was he-1d for the required duration.
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The reactor coolant temperature was maintained above the nil ductility transition temperature.
Corrective actions have been taken to resolve the deficiencies
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identified during the hydrostatic test.
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The test results have been reviewed and approved by the appropriate personnel.
No violations or deviations were identified in the areas inspected.
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Module 7 Readiness Review (70307) (72500)
The inspectors reviewed the 10 CFR 50, Appendix J commitments identified in Module 7 of the Readiness Review.
The objective of this review was to verify that the licensee had performed an appropriate assessment of the Appendix J program, and to independently determine its adequacy. Based on the present program completion level, the inspectors had no findings in the Appendix J program.
The inspectors determined that the licensee had identified the appropriate implementation documents for each commitment and had also adequately verified the commitments in the implementation documents.
The inspectors also reviewed the fuel movement commitments that are included in Module 7.
Selected commitments were compared with the appropriate source documents to determine if the commitment had been adequately captured.
These commitments were then verified to be incorporated into the correctly specified implementation document. Although this effort was hindered by the large number of fuel movement documents listed as "in draft," the inspectors did determine that the licensee had at minimum demonstrated an awareness of
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the commitments and implementation regarding fuel movement.
No violations or deviations were identified in the areas inspected.
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Inspector Followup Item Review (92703)
(Closed) IE Bulletin 84-03, concerning the refueling cavity water seal. The inspectors reviewed the design of the Vogtle refueling cavity water seal as
it applies to IE Bulletin 84-03.
The seal assembly is of the passive
mechanical type in lieu of the inflatable pneumatic seal discussed in the bulletin. This item is considered closed.
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