IR 05000395/1982040

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IE Insp Rept 50-395/82-40 on 820608-11.No Noncompliance Noted.Major Areas Inspected:Radiation Protection,Liquid, Solid & Gaseous Sys
ML20058B805
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 07/01/1982
From: Barr K, Peery W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20058B800 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM 50-395-82-40, NUDOCS 8207260152
Download: ML20058B805 (4)


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'o UNITED STATES -

'h NUCLEAR REGULATORY COMMISSION c

c REGION 11

o 101 MARIETTA ST., N.W., SUITE 3100 o

ATLAN TA, GEORGIA 30303

Report No. 50-395/82-40 Licensee:

South Carolina Electric and Gas Company Columbia, SC 29218 Facility Name:

Virgil C. Summer Nuclear Station Docket No. 50-395 License No. CPPR-94 Inspection at Summer site near Jenkinsville, SC 6/zr/FL Inspector:_

u Date Signed W. W. Peery Approved by:

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P. Barr, Sectic. Chief Ddte Signed T echnical Inspec 'on Branch Division of Engineering and Technical Programs l

SUMMARY Inspection on June 8-11, 1982 Areas Inspected This routine, unannounced inspection involved 22 inspector-hours on site in the areas of radiation protection, liquid, solid and gaseous systems.

Results Of the three areas inspected, no items of noncompliance or deviations were

identified.

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REPORT DETAILS (

1.

Persons Contacted Licensee Employees

  • W. A. Williams, Jr., General Manager, Nuclear Operations
  • 0. S. Bradham, Station Manager

"V. R. Albert, Assistant Manager-Support Services

  • A.

R. Koon, Technical Services Coordinator

  • L. A. Blue, Director of Health Physics
  • H. C. Fields, Technical Services Engineer
  • H. I. Donnelly, ISEG Engineer
  • J. Ferris, Technical Support Engineer
  • G. Guy, Technical Support Engineer
  • J. Cox, Health Physics Supervisor
  • J. Bellmore, Health Physics Supervisor
  • S. Howze, Nuclear Licensing Engineer Other licensee employees contacted included three technicians.

Other Organizations

  • C. Bowman, Startup Engineer, Westinghouse NRC Resident Inspector
  • J. L. Skolds
  • Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on June 11, 1982, with

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those persons indicated in paragraph 1 above.

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Licensee Action On Previous Inspection Findings Not inspected.

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Unresolved Items l

Unresolved items were not identified during this inspection.

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5.

Inspector Follow-up Items a.

(Closed)(IFI) 395/80-33-07, through discussions, records review and inspection of each installed area radiation monitor and associated read-outs, the inspector determined that the installation and cali-bration of the area radiation monitoring system was complete, b.

(0 pen)(IFI) 395/82-07-03, Damaged prefilters had not been replaced.

The licensee plans to change all prefilters in the latter stages of plant preparation for startup. This item will be reviewed af ter the

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completion of the filter changes.

c.

(Closed)(IFI) 395/82-07-04, Plant procedures HPP-709, Release of Radioactive Gaseous Effluents and SOP-119, Waste Gas Processing were being revised at the time of the last inspection.

The completed procedures were reviewed and the inspector had no further questions.

d.

(Closed)(IFI) 395/82-21-01, The licensee now has eleven Health Physics technicians qualified in accordance with ANSI 18.1-1971 as required by Technical Specification 6.3.1.

In addition to the five Health Physics Supervisors previously reported, the licensee also has eight additional health physics technicians continuing training. The inspector had no further questions.

e.

(0 pen) (IFI) 395/82-21-02, The installation of the solid waste solidi-fication system was not complete. A licensee representative stated that the system should be completed within about one week (from 6/11/82).

f.

(0 pen)(IFI) 395/82-21-03, Measurement of Hood Face Velocities.

The results of measurements of fume hood face velocities were reviewed and the inspector hao no further questions.

However, face velocity mea-surements had not been made on sample hoods. The inspector or resident

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inspector will review the results of sample hood measurements when they are completed.

g.

(Closed)(IFI) 395/82-21-04, Gaseous Radioactivity Monitors. Documenta-tion did not include verification that flow from sample points was coming from the intended area. A review of test records revealed that the documentation was available and the inspector had no further questions.

h.

(Closed)(IFI) 395/82-21-05, Ventilation System Filter Testing.

The inspector reviewed records of ventilation filter testing and determined that residence times and flow distributions were included.

The inspector had no further questions, i.

(Open)(IFI) 395/82-21-06, Waste Gas System. Testing of the waste gas system had not been completed.

A licensee contractor representative stated that the tests should be completed during the week of June 13, 1982. The test results will be reviewed on a subsequent inspection.

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6.

Post Accident Sampling (NUREG 0737,Section II.B.3)

Post accident sampling capability was inspected for those aspects contained in Facilities Radiation Protection Section (FRP) Memorandum, dated June 10, j

1982, Subject - Inspection of facilities to NUREG 0737, which includes:

sample collection; sample transport; sample handling and disposal; adequacy of system (s) to perform intended mechanical functions; adequacy of operating procedures and personnel training. The Summer Station has one post acci-

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dent containment sampling system on the 463 elevation of the Auxiliary Building and a backup sampling system in the fuel pool storage area.

Installation of both systems was observed to be complete. The inspector observed the installation of sample collectors into the system by a Health Physics Technician. Lead lined stainless steel containers are provided for transport of the samples. The system has the capability to dilute samples to reduce radiation levels, if necessary.

The system has been tested and found to be functional. Through discussion and review of records the inspector determined that Health Physics personnel have been trained in the use of the sampling system.

Procedure HPP-920, Post Accident Reactor Building Atmospheric Sampling, dated January 28, 1982, was reviewed in relation to the systems and the inspector had no further questions.

7.

Mitigating Core Damage (NUREG 0737,Section II.B.4)

In accordance with the FRP Section Memorandum referenced in paragraph 6 above, this inspection effort was limited to Health Physics personnel training. Discussions with various Health Physics personnel and review of training records revealed that training in this area is included and con-tinuing.

8.

Accident Monitoring (Section II F.1) - Inplant Radiation Monitoring (Section III.D.3.3)

The licenseee has provided capability for noble gas monitoring and iodine l

and particulate samples during accident conditions. A high range contain-ment monitor has also been provided.

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