ML19309C198

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1979 Annual Status Rept 15
ML19309C198
Person / Time
Site: Vallecitos Nuclear Center
Issue date: 02/29/1980
From:
GENERAL ELECTRIC CO.
To:
Shared Package
ML19309C194 List:
References
NUDOCS 8004080289
Download: ML19309C198 (5)


Text

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O VALLECITOS BOILING WATER REACTOR ANNUAL REPORT NO. 15 (Deactivated)

License DPR-1 Docket 50-18 8004080 2F7

VALLECITOS BOILING WATER REACTOR ANNUAL REPORT No. 15 (Deactivated)

The status of the Vallecitos Boiling Water Reactor (VBWR) during the calendar year of 1979, is described in this fifteenth report of the deactivated facility, in conformance with License DPR-1, Docket 50-18, Amendment 19, Paragraph 5.d.2.

I.

SUMMARY

The facility remained essentially in a static condition as described in Annual Report No. 14.

Entry into the containment building was made for routine radia-tion surveys and for a check of general conditions throughout the building to verify the unchanged condition of the facility. The reactor vessel water level was monitored and remained essentially constant.

II. STATUS OF THE FACILITY A.

CONTAINMENT BUILIDNG No changes were made during the report period.

B.

GENERAL SYSTEPG No changes were made during the report period.

III. PERIODIC INSPECTIONS Inspections of the facility were continued on a routine basis. The annual air samples and radiation and contamination surveys of the containment vessel are given in Table 1 of this report.

The poor air quality in the containment building required that entry be made with self-contained breathing apparatus. The air quality is a result of stagna-tion, and although the oxygen levels are normal, the air is unbreathable because of odors. Safety considerations involving the use of breathing equipment prevented entry into some areas of the containment.

IV.

RADIATION AND CONTAMINATION Radiation and contamination surveys of the facility indicate the levels in all cases were well below the limits for any safety concern.

1

i V.

CONCLUSION In our opinion, the deactivated Vallecitos Boiling Water Reactor continues to be maintained in a safe condition, commensurate with its shutdown status.

The methods of inspection and control of safety related items ensure maximum protection for the public and the General Electric Company.

t GENERAL ELECTRIC COMPANY Irradiation Processing Operation By D. L. dilliland, Manager Reactor Irradiations 2

0 TABLE 1.

Radiation and Contamination Report Contamination Levels Radiation Surface (Smears)

Airborne Levels Beta-Gamma Beta-Gamma (mR/h Gamma)

(c/m/100 cm2 x 103)

(uCi/cc x 10-10) 12 /78 12/79 12/78 12/79 12/78 12/79 Reactor Enclosure Main Floor - General Field 0.5 0.5 03 0.2 0.11'

<0.018 1.

Top of Missile Shield, Field 0.5 03 0.3 0.1 NA NA 2.

Top of Spent Fuel Pit Cover 1.25 1.0 0.3 0.1 NA NA 3

Pit (down 3 ft) 1 75 1.7 NA NA NA NA Reactor Basement 1.

Upper Level, Field 14 10 NA NA NA NA 2.

Bottom Wall, Ladder 10 10 0.5 0.5 NA NA v

3 East Ladder, Bottom 40 40 3.5 0.2 NA NA 4.

West Ladder, Bottom 25 25 0.5 0.1 1.70' O.26' 5.

Between Recirculation Pumps 2 feet off Deck 50 45 NA NA NA NA 6.

RCP No. 1 Surface 40 30 5.0 0.1 NA NA 7.

RCP No. 2 Surface 40 25 3.0 0.9 NA NA 8.

Downcomers 60 60 0.9 03 NA NA 9.

Downcomers behind Reactor Shield 50 40 2.5 2.0 NA NA 10.

Main Steam Line 6

10 5.0 03 NA NA Enclosure Stack-Outside Surface

<1

<1

<0.1

<0.1 NA NA Main Valve Pit Valve Pit Lines and Valves

<1

<1

<0.1

<0.1 NA NA NA indicates readings not taken or not analyzed.

"24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> decay.

9 NOTE:

Radiation levels, surface smears and air samples will vary from survey to survey as they are taken in general areas rather than at specific locations.