IR 05000018/1980001
| ML19305E600 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos Nuclear Center |
| Issue date: | 04/08/1980 |
| From: | Book H, Fish R, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19305E596 | List: |
| References | |
| 50-018-80-01, 50-18-80-1, NUDOCS 8005200094 | |
| Download: ML19305E600 (4) | |
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O U. S. NUCLEAR REGUUsTORY COW.ISSION 0FFICE OF ISSPECTION AND ENFORCE!ENT
REGION V
Report No.
50 '8/80-01 Docket No.
50-18 License No.
npp_1 Safeguards Group Licensee:
General Electric Comoany Vallecitos Nuclear Center M easanton. California 94566 Facility Name:
- Vallecitos Boiling Water Reactor (VRWR)
Inspection at:
Pleasanton. California
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Inspection conc'ucted: February 25 and March 2-3. 1980
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Inspectors:
R. F. Fish, Radiation Specialist
/Date Signed
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Date Signed
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Approved by:
te en E n. 4enslaws/i,Ch ef, Reactor Radiation Safety Section Ddte' Signed O Y "3 O
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Approved By:
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e H. E. Book, Chief
' Dale Signed Fuel Facility & Materials Safety Branch Sumry:
Inspection on February 25 and March 2-3, 1980 (Recort No. 50-18/80-01)
f Areas Inspected: Routine unannounced inspection of organization, procedures, records,' security, annual reports, audits, tour of facility and independent measurerrents. The inspection involved six (6) hours onsite by one inspector.
' Resul ts : No items of noncompliance or deviations were identified.
RV Form 219 (2)
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DETAILS 1.
Persons Contacted _
W. P. Springsteen, Supervisor, Planning and Materials
- E. Strain, Nuclear Safety Engineer C. Hooker, Supervisor, Radiological Protection J. Reck, Radiation Monitor
- Present at exit interview.
2.
Organization Access control and routine inspection of VBWR are the responsibility of the GETR Operations Manager. Radiation surveys have been made by Radiological and Environmental Protection Unit monitors.
The Nuclear Safety Technology Unit has performed twice a year audits of activities to assure compliance with the license and other regulatory requirements.
No items of noncompliance or deviations were identified.
3.
Procedures Procedures relating to the inspection, access control and use or mod-ification of the VBWR were found to be as described in Paragraph 3 of IE Inspection Report No. 50-18/76-01.
The inspection disclosed that only minor changes to these procedures have been mada since the March 2,1978 inspection. These changes (OCN's) were made 1. conformance with the administrative requirements and the required approvals had been obtained.
No items of noncompliance or deviations were identified.
4.
Records The licensee's records consist of a log book, weekly patrol sheets, and survey results.
Each weekly patrol and all entrances into the VBWR have been recorded in the log book.
The routine surveys have been performed on an annual frequency.
The records generated during 1978,1979 and 1980 (through February 29) were examined on a random basis. The log book appeared to record all activities involving VBWR.
The patrol sheets examined were being completed in accordance wi.th the procedure. The survey records showed radiation levels varied over the range of 0.5 to 60 mR/hr inside the containment building. Accord-ing to the records air activity varied over the range of 0.1 1.7 x 10-10
uCi/cc and the maximum removable activity was 900 dpm/100 cm. These survey results were similar to those of earlier surveys.
No items of noncompliance or deviations were identified.
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Security The facility has been kept in a locked condition. GETR operations has tontrol of the keys to the VBWR facility locks.
Prior to each entry, monitors check the atmosphere inside the facility for explosive conte 1t and airborne activity.
The weekly patrol by GETR operations personhal included visual confirmation that the facility was in a locked condi tio1.
No itms of noncompliance or deviations were identified.
6.
Annual Reports The licensee submitted annual reports for the years 1977 and 1978 to the Director, Office of Nuclear Reactor Regulation, NRC. The report for the year 1979 was being reviewed and the licensee expected to submit it in the near future. The reports were examined and found to contain the information required by license condition 5.d.(2).
No items of noncompliance or deviations were identified.
7.
Tour of Facility and Independent Measurements The visit to the VBNR did not disclose any changes in the posting, entrance warning device, or facility since the March 2, 1978 inspec-tion. Protective clothing must still be worn by persons entering the VBWR. During the visit radiation measurements were selectively taken with a Region V beta gama survey meter, Serial No. NRC 377, that was calibrated on February 18, 1980.
On the main floor of the containment building radiation levels varied from background to 2.5 mR/hr. The maximum radiation at the base of the stack was 2.5 mR/hr.
Several wipes were taken on the ground level floor of the containment builging. The maximum removable activity detected was about 215 dpm/100 cm. The wipes were counted in the Region V M4C Podel PC-55 proportional counter.
No items of noncompliance or deviations were identified.
8.
Audit The Nuclear Safety Technology Unit audited the VBWR activities for compliance with the license and other regulatory requirements on June 27-28, 1978, February 4-5, 1979 and December 18-19, 1979..The February 1979 audit identified 3 patrol sheets that were undated. The December 1979 audit identified 3 minor deficiencies.
Corrective actions for the 3 deficiencies were documented; however, corrective action for
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-3-one of the items will not be completed until May 1980 because it might involve a technical specification change. The December 1979 audit involved the preparation of (1) a description of the scope of the audit, (2) an audit plan and (3) a check list of audit items. According to the licensee future audits will also require the preparation of these items prior to performing the audit.
No items of noncompliance or deviations were identified.
9.
Exit Interview On March 19, 1980 the inspector met with the following licensee personnel:
R. Darmitzel, Manager of IPP Section; P. Kachel, Manager, GETR Opera-tions; D. Smith, Acting Analyst; E. Strain, Nuclear Safety Engineer; P. Webb, Manager, Radiological and Environmental Protection.
The scope of the inspection and the findings were presented.
The licensee was informed that no items of noncompliance were identified.
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