ML20210G877

Getr Annual Rept 27

ML20210G877
Person / Time
Site:	Vallecitos File:GEH Hitachi icon.png
Issue date:	12/31/1985
From:	Cunningham G, Titus G GENERAL ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8604020613
Download: ML20210G877 (6)

Text

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t GENERAL ELECTRIC TEST REACTOR ANNUAL REPORT NO. 27 LICENSE TR-1 DOCKET 50-70 NUCLEAR TECHNOLOGIES & FUEL DIVISION e GENERAL ELECTRIC COMPAfiY VALLECITOS NUCLEAR CENTER, PLEASANTON, CALIFORNIA 94566

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GENERAL ELECTRIC TEST REACTOR ANNUAL REPORT NO 27 I. INTRODUCTION This annual report, covering the period January 1, 1985 to December 31, 1985, for the General Electric test Reactor (GETR), is submitted in fulfillment of the requirements of Section 3.D(4) of License TR-1 and 10CFR50.59(b).

II. OPERATING

SUMMARY

On October 24, 1977, the General Electric Test Reactor was ordered to remain shut down, following a routine outage, pending further order from the Nuclear Regulatory Commission. The order was based on an interpretation of the geology of the Livermore Valley as shown on the U.S. Geological Survey (USGS) open file report number 77-689 and a preliminary evaluation of evidence of faulting in a trench dug at the Vallecitos Nuclear Center. The reactor was shut down on October 27, 1977, and has remained in this condition through December 31, 1985.

On April 13, 1983, the NRC rescinded the October, 1977, Order to Show Cause based on information presented to the Atomic Safety and Licensing Board.

Concurrently, the NRC issued Amendment 12 to License TR-1 which establishes the modifications to the GETR necessary to permit startup of the reactor. A June 26, 1985 letter, supplemented July 15, 1985, requested amenament of the pending GETR license renewal to a possession only license.

III. STATISTICS

1. Containment Building Evacuations and Isolations There were no isolations or evacuations in 1985.

2. Personnel (As of December 31,1985)

Licensed Senior Reactor Operators (SR0s) - 0 IV. REACTOR AND SYSTEMS COMPLIANCE TESTS Amendment No. 9 to the GETR License TR-1 issued on October 14, 1982, deleted the requirements to conduct certain compliance tests, specifically those tests not associated with containment building integrity.

Amendment No. 11 to the GETR License TR-1 issued on February 23, 1983, deleted the requirement to maintain containment building integrity and deleted the requirements to conduct compliance tests associated with containment building integrity while there is no irradiated fuel or irradiated fueled experiments in the containment building.

No compliance tests were performed during 1985.

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GETR Annual Report No. 27 V. MALFUNCTION OF CONTROL AND SAFETY SYSTEMS All safety systems and automatic control systems are deactivated by modifications made to the plant during 1983. These changes have omitted the need for controls for the Primary Coolant System and the Containment Building Systems.

VI. CHANGES AUTHORIZED BY MANAGER, REACTOR OPERATIONS & SUPPORT SERVICES Pursuant to 10CFR50.59(a), the Facility Manager authorized changes during the report period. These changes were authorized in accordance with APED-5000-A, Paragraph 3.3.1. The changes completed in 1985 are isted below.

1. Move Site Alarm to Building 102B Description of Change:

The central site alarm panel was relocated from GETR control room to the Security Building (1028).

Safety Analysis:

This change relocates the site central alarm panel to Building 1028, which is manned 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, and increases the reliability of the site alarm system. The new system embodies newer equipment and eliminates a signal multi-plexing link that required much oversight and maintenance. It provides a higher reliability system requiring less maintenance and for which replacement parts are available.

2. Environmental Program Sample Change Description of Change:

As the result of a new Regional Water Quality Control Board permit and a review of sampling results for radioactive materials, changes in the environmental sampling program were implemented. The changes eliminated some samples, added others, and modified the sampling frequency of other samples.

Safety Analysis:

Changes in radiological sampling were made as the result of an analysis of environmental data gathered in the period 1980-1984 The analyses showed that there was reasonable consistency between samples indicating that many were redundant. Further, because of changes in site activities (GETR shutdown, termir.ation of isotope recovery and elimination of the Advanced Fuels Laboratory),- potential sources for release of activity have been reduced or eliminated.

r-s GETR Annual Report No. 27

3. Removal of Constant Air Monitors (CAM's) and Motor-Air Samplers From Service Description of Change:

Two remaining Constant Air Monitors (CAM's) and two Motor-Air Samplers were removed from service.

Safety Analysis:

No work activity had been performed in the GETR containment in 1985 and none was anticipated in the near future. Air activity had varied very slightly over a two-year period indicating no further need for either monitoring or sampling containment air. When entries are required in the future, air samples will be collected in advance. Access to the containment is stringently restricted.

4. Removal Remote Area Monitoring (RAM) Stations From Service Description of Change:

The seven remaining Remote Area Monitoring (RAM) Stations will be removed from service.

Safety Analysis:

Activities requiring this category of monitoring no longer are performed at GETR. Access to the containment and to the area surrounding GETR is restricted. Containment entries will be monitored with an operating dose rate instrument; therefore, continued RAM operation is unnecessary.

5. Removal of Pool Submersible Demineralizer Description of Change:

The submersible demineralizer was removed from the pool in conjunction with GETR containment closure. Water quality deterioration resulting from this change will have no adverse effects.

Safety Analysis:

There are no nuclear or industrial safety implications of this change.

VII. CHANGE IN ORGANIZATION There were no changes in organization.

VIII. SIGNIFICANT CHANGES IN PROCEDURES During 1985, there were no changes to the Standard Operating Procedures.

5 GETR Annual Report No. 27 IX. RADIATION LEVELS AND SAMPLE RESULTS AT ON-SITE AND OFF-SITE MONITORING STATIONS The data below are from sample and dosimeter results accumulated during 1985.

These data are for the entire VNC site aad include the effects of operations other than the GETR. The type and locations of the samples are described in APED-5000-A.

1. Air Monitors. (Yearly average of all meteorological stations.)

Alpha Concentration:

Maximum < 5.90 x 10 15 pCi/cc Average < 3.05 x 10 15 pCi/cc Beta Concentration:

Maximum < 3.20 x 10~13 pCf/cc Average < 4.70 x 10~14 pCi/cc

2. Gamma Radiation. The integrated yearly dose results for the year 1985 as deterininen from evaluation of site perimeter environmental monitoring dosimeters showed readings within normal dosimeter background (i.e., the background shown on duplicate TLDs stored in non-radiation areas at the VNC and at the facilities of the TLD dosimeter processor).

3. Vegetation. No alpha, beta, or gamma activity attributable to activities at the GETR facility was found on or in vegetation in the vicinity of the site.

4. Water. There was no release of radioactivity in water or to the ground water greater than those limits specified in 10CFR20, Appendix B, Table II, Column 2.

5. Off-Site. Samples taken off the site indicate normal background for the area.

X. CONCLUSION The conditions at the GETR reflect a year of-safe shutdown conditions.

GENERAL EL TRIC COMPANY Irradiati Processing Operation By: M%

G('41. Tit 0s, Manager l Reactor Operations & Support Services m

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GEllERAL $ ELECTRIC NUCLEAR ENERGY SU$1NE55 OPERATIONS GENERAL ELECTWC COMPANr e VAllECTOS NUCLEAR CENTER e PLEAsANTON, CAUFORNIA 94566 March 25, 1986 Dr. H. R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D.C. 20555

Reference:

License TR-1, Docket 50-70

Dear Dr. Denton:

Enclosed.are'three signed and forty conformed copies of Annual Report No. 27-for the General Electric Test Reactor.

Sincerely, s

G. E. Cunnin am Senior Licensing Engineer (415)862-4330

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