ML18082A145

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Forwards Updated Info Re Implementation of short-term Lessons Learned Task Force Requirements.Evaluation Will Be Performed of Expected Radiation Levels Prior to Initiation of Special Low Power Test Program
ML18082A145
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/03/1980
From: Mittl R
Public Service Enterprise Group
To: Parr O
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8004110431
Download: ML18082A145 (5)


Text

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0 PS~G9 Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 April 3, 1980 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.

20555 ATTENTION:

Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management Gentlemen:

TMI LESSONS LEARNED NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 PSE&G hereby transmits updated information concerning imple-mentation of Lessons Learned requirements.

The information enclosed is in the form of new and replacement pages to be inserted in the enclosure to our submittal of January 4, 1980.

Our letter dated March 31, 1980 discussed the special low power test program, including evaluation of expected radi-ation levels following completion of the test program.

As a point of clarification, it is our intent to perform an evaluation of the expected radiation levels prior to initi-ation of the special low power test program.

Should you have any questions, do not hesitate to contact us.

Enclosure The Energy People Rrt;;;;;rs, R. L. Mittl General Manager -

Licensing and Environment Engineering and Construction

-r-95-0942

I I

I 0 PS~cP Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 April 3, 1980 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.

20555 ATTENTION:

Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management Gentlemen:

TMI LESSONS LEARNED NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 PSE&G hereby transmits updated information concerning imple-mentation of Lessons Learned requirements.

The information enclosed is in the form of new and replacement pages to be inserted in the enclosure to our submittal of January 4, 1980.

Our letter dated March 31, 1980 discussed the special low power test program, including evaluation of expected radi-ation levels following completion of the test program.

As a point of clarification, it is our intent to perform an evaluation of the expected radiation levels prior to initi-ation of the special low power test program.

Should you have any questions, do not hesitate to contact us.

Enclosure The Energy People Very trwly y

rs,

'D4 ',

r.,/ 4 / ~t R. L. Mittl General Manager -

Licensing and Environment Engineering and Construction 95-09(

Calculational Methods and Information Dissemination -

The calculational method used for converting instrument read-ings to release rates will be provided in the instruc-tions for interpreting monitor response.

  • Calculations using the ORIGEN code are used to provide spectrum dis-tribution and average energy values.

Analysis indicates that within a few hours after reactor shut-down, Xenon 133 becomes the predominant isotope.

The channel read-ings will be recorded and the information will be posted on an emergency status board to be located in the on-site technical support center.

Since the channel measures the production of ion pairs produced in the tube, calibration is done by determining the GM tube plateau.

This interim modification will be operational by April 4, 198 0.

Iodine and Particulate Monitoring Radioactive effluent monitors installed at Salem 2 were designed to monitor iodine and particulates during normal and accident conditions.

Continuous iodine monitoring of the containment and unit vent is provided through the use of two 2 x 2 inch digital gamma scintillation detectors.

One scintillator is unattenuated and the other utilizes a lead spacer to desensitize detector response.

Detector response is continuously analyzed by a minicomputer to determine M P79 54 01/33.2

-25b-Salem 1 & 2 APR 0 3 1980

the iodine accumulation rate on the impregnated charcoal filter.

In order to minimize Compton scatter, the iodine channels are provided with electronics to enable "viewing" the count rate above the iodine 364 keV photopeak.

The channels are also equipped with Americium stabilization circuitry to eliminate gain shift due to temperature.

Continuous monitoring of particulates is accomplished by utilizing moving filter paper with a speed adjustable from 1-inch to 32-inches per hour.

Station procedures provide for remote sampling of the containment in the event of a containment isolation signal.

Vital power is available for remote sampling.

The physical size of the Auxiliary Building makes it impractical to install fixed sampling stations.

In addition, the development of "hot spots" would also make fixed sampling locations impractical.

Portable equipment available at the plant for iodine sampling includes high-volume air samplers, scaler timer ratemeter - single channel analyzer, 2" x 1/2" Na! gamma scintillation detector, alternators, battery packs and lead shielding.

A Multichannel analyzer will be installed in a remote

. location for detailed energy spectrum analyses.

A remote location will assure a low background and will eliminate Compton scatter effects.

Written procedures will be M P79 54 01/33.3

-25c-Salem 1 & 2 APR D 3 1980

i-__,,

prepared to assess high iodine and particulate releases.

These procedures will identify the precautions to be taken for sampling in high radioactivity areas, personnel exposure time determination and instructions for handling contaminated filters, including the use of tongs and shielded containers for transportation of samples.

If the expected iodine concentration is high, collection times will be adjusted accordingly and the multi-channel analyzer desensitized as appropriate.

These procedures will be available prior to low power testing.

2.

The Salem design provides for iodine sampling by adsorption on charcoal cartridges, followed by onsite laboratory analysis.

3.

The containment high range monitors presently have the fqllowing maximum detection ranges:

Unit 1:

Unit 2:

104 R/hr.

107 R/hr.

M P79 54 01/33.4

-24d-Salem 1 & 2 APR 0 3 1980