IR 05000424/1986008
| ML20141N146 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/26/1986 |
| From: | Jape F, Larry Nicholson, Schnebli G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20141N143 | List: |
| References | |
| 50-424-86-08, 50-424-86-8, NUDOCS 8603040413 | |
| Download: ML20141N146 (4) | |
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UNITED STATES
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'o NUCLEAR REGULATORY COMMISSION
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nEGIOi4 ll n
j 101 MARIETTA STREET,N.W.
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ATLANTA, GEORGI A 30323
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Report No.: 50-424/86-08 Licensee:
Georgia Power Company P. O.' Box 4545 Atlanta, GA 30302 Docket No.:
50-424 License No.:
CPPR-108 Facility Name: Vogtle Unit 1 Inspection Conducted:
February 10-14, 1986 Inspectors: C1, (?, Ta-u b/
WM,IfI-p L. Nicholson/
Date Signed-0, $fs Z/2&/K G. Schnebli /
Date Signed Accompanying Personnel:
A. R. Herdt, Chief, Engineering Branch D. M. Collins, Chief, Emergency Preparedness and Radiological Protection Branch F. Jape, Chief, Test Program Section M. V. Sinkule, Chief, Reactor Projects Section i
Approved by:
W F. Jape, Secti6n Chief V
Date Signed
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Engineering Branch Division of Reactor Safety SUMMARY Scope: This routine, announced inspection involved 66 inspector-hou'rs on site in the areas of review of primary plant hydrostatic test procedure, observation of residual heat removal system preoperational testing, review of the 2verall preoperational test program, and the second corporate management meeting.
Results: No violations or deviations were identified.
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REPORT DETAILS
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Persons Contacted Licensee Employees
- D. O. Foster, Vice President, Project Support
- A. L. Mosbaugh, Integrated Test Program Manager
- H. P. Walker, Manager, Unit Operations
- S. A. Bradley, Nuclear-0perations
- G. E. Spell, QA Engineering Supervisor
- C. E. Belflower, QA Site Manager - Operations i
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- E. M. Dannemiller, QA Senior Engineer -- Operations J. G. Aufdenkampe, Lead Integrated Test Supervisor J. A. Bailey, SCS - Licensing
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J. L. Leamon, SCS - Licensing R. H. Pinson, Vice President Construction C. W. Hayes, QA Manager
D. S. Read, QA Manager
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A. Desrosiers, HP Manager i
Other licensee employees contacted included engineers, technicians, operators, security force members and office personnel.
Other Organizations H. M. Handfinger, Preop. Test Superintendent Bechtel i
S. Day, Field Tect Superintendent, Bechtel J. Gosnell, ANI, HartfJrd Steam Boiler Inspection and Ins. Co.
S. Shelton, Test Writing Supervisor, Pullman Power Products
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i NRC Resident Inspectors
- J. F. Rogge, Senior Resident Inspector
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- H. H. Livermore,-Senior Resident Inspector - Construction i
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on February 14, 1986, with i
those persens indicated in paragraph 1 above.
The inspector described the
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areas inspected and discussed in detail the inspection findings.
No i
dissenting coments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
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3.
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 this inspection.
5.
Overall Preoperational Test Program Review (70301)
In the course of this inspection, the inspectors completed the review of the Preoperational Test Program.
See Inspection Reports 50-424/85-24, 50-424/85-30 and 50-424/85-41 for previous inspections covering the Test Program.
The review during this inspection consisted of the following:
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Discussions with preoperational test personnel in the areas of test scheduling, procedure status and general conduct of testing.
In addition, preparations for the Reactor Coolant System (RCS) Hydrostatic Test, which is presently scheduled for February 28, 1986, were discussed in detail.
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Discussions were also held with Quality Assurance Personnel and Authorized Nuclear Inspectors (ANI) concerning inspection points during the RCS Hydrostatic Test and problems encountered during the-performance of this test at other sites.
Within the areas examined, no violations or deviations were identified.
6.
Reactor Coolant System Hydrostatic Test Procedure Review (70362)
The inspectors reviewed revision 1 to test procedure number 1-300-03, Reactor Coolant System Hydrostatic Test, to verify that the test procedure met the requirements and commitments specified in ASME Code,Section III, Division 1, Subsection NB, Ariticle NB-6000; Regulatory Guide 1.68; Safety
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Evaluation Report; and the Final Safety Evaluation Report chapter.-
14.2.8.1.9.
The inspectors verified that the test procedure contained the required test temperatures, test pressures in relation to f.SME Code requirements, test gage calibration requirements, inspection points, prerequisites, N stamp documentation and QC verification of the test results.
The test procedure does require maintaining hydrostatic test pressure for a minimum of 10 minutes before initiation of the examination for leakage.
Within the areas inspected, no violations or deviations were identified.
7.
Preoperational Test Witnessing (70312)
During this inspection, the inspectors witnessed portions of the Residual Heat Removal System Preoperational Test, procedure 1-3BC-01, Section 6.14, lerification of Cold Leg Injection.
The following areas were observed:
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Testing was conducted in accordance with approved procedures and the
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latest revision of the test procedure was available and in use by personnel conducting the test.
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All required test procedure prerequisites were met.
Changes to the procedures were accomplished in accordance with the
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licensee's administrative controls.
Adequate coordination existed among the responsible organizations to
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conduct the test properly and in a controlled manner.
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Test data were collected and recorded as required by the procedure or other administrative instructions.
Within the areas examined, no violations or deviations were identified.
8.
Second Corporate Management Meeting (30301)
NRC Region II conducted a management meeting with key corporate and plant operating personnel to review in detail the NRC inspection program as it relates to preoperational and startup testing activities.
This presentation included an explanation of the Region II organization and staffing.
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The licensee presented his operating organization and supporting staff as it pertains to both construction and operations.
The licensee also provided status of construction activities, operating staff experience, manpower requirements and the interfacing used to turn systems over the operating staff from construction.
Following the licensee presentation, Region II management addressed the major areas of inspection which will occur during the preoperational and startup phases of operation.
Areas discussed included the inspection of Quality Assurance, Health Physics and Radwaste Programs, Emergency Preparedness, Security and Safeguards, Fire Protection, Preoperational and Startup Test Programs.
Emphasis was placed on assurance that Technical Specifications and plant procedures are thoroughly walked down and reflect the as-built plant systems.
Experiences and resolutions to past problems concerning the preoperation inspection program were reviewed during the meeting.
9.
Followup of Event Reports (92700)
(Closed) CDR 80-04, Rod Drop Analysis Reportable per Final 022080 Letter This item addresses a concern for the potential of an unanalyzed power overthoot while in automatic rod control following selected dropped rod events without immediate reactor trip.
This overshoot could lead to calculated departure from nuclear boiling (DNB) ratios lower than those used in analysis.
The NRC has reviewed and approved the Westinghouse topical report on the subject as documented in Supplement I, Section 15.4.3 of the Vogtle Safety Evaluation Report.
This item is considered closed based on this approval.
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