IR 05000424/1986052

Insp Rept 50-424/86-52 on 860602-06.No Violations or Deviations Noted.Major Areas Inspected:Readiness Review Module 7 & Preoperational Test Witnessing

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: IR 05000424/1986052 ML20203C029
References
50-424-86-52, NUDOCS 8607180345
Download: ML20203C043 (4)

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SR FE4 UNITED STATES o NUCLEAR REGULATORY COMMISSION 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 Docket No.: '50-424 License No.: CPPR-108 Facility Name: Vogtle 1

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Inspection Conducted: June 2-6, 1986 Inspectors: 84 L. E. N1 olson D1te Signed G c~ A LanJJ 7fil Macdonal p ,

Date Signed *

Approved by: &M O #'/d . // b F. Jape, Sectron Chief f Date Signed 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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REPORT DETAILS

. Persons Contacted Licensee Employees

• C. E. Belflower, QA Site Manager (OPS)

• 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 operator NRC Resident Inspector

• J. F. Rogge, Senior Resident Inspector, Operations

• Attended exit interview 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 finding No dissenting comments were received from the licensee. ~ The following new item 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 inspectio . Licensee Action on Previous Enforcement Matters l This subject was not addressed in the inspectio . Unresolved Items Unresolved items were not identified during the inspectio I l

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i S. Preoperational Test Witnessing (70433) l 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 procedure Latest revisions of the approved test procedures were available and in use by personnel performing the test Test equipment required by the procedures was calibrated and installe Test data were properly collected and recorde Adequate coordination existed among personnel involved in the tes Test prerequisites were me Temporary modifications such as jumpers were installed and tracked in accordance with administrative control Problems encountered during testing were properly documente 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-1-86-183 No violations or deviations were identified in the areas inspecte . 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:

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Test changes were made in accordance with the licensee's administrative control Changes made to the procedure did not alter the intent of the tes i

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Water quality was maintained in accordance with the requirements specifie The hydrostatic test pressure was he-1d for the required duratio The reactor coolant temperature was maintained above the nil ductility transition temperatur Corrective actions have been taken to resolve the deficiencies identified during the hydrostatic tes The test results have been reviewed and approved by the appropriate personne No violations or deviations were identified in the areas inspecte . 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 document 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 capture 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 ,

the commitments and implementation regarding fuel movemen No violations or deviations were identified in the areas inspecte ' 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 84-0 The seal assembly is of the passive 1 mechanical type in lieu of the inflatable pneumatic seal discussed in the bulletin. This item is considered close .