ML20141N880

Forwards Addl Info Re Changes to Facility post-accident Sampling Sys,Per 860218 Meeting W/Nrc & 860220 Telcon.Data Re Induced Gamma Radiation & Accuracy of Portions of Sys Affected by Mods Will Be Provided When Available

ML20141N880
Person / Time
Site:	Rancho Seco
Issue date:	03/13/1986
From:	Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Miraglia F Office of Nuclear Reactor Regulation
References
RJR-86-97, TAC-60632, NUDOCS 8603180236
Download: ML20141N880 (5)

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gsuun SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, P.O. Box 15830. Sacramento CA.958521830, (916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA RJR-86-97 March 13,1986 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTNENTION FRANK J MIRAGLIA JR DIRECTOR DIVISION OF PWR LICENSING-B U S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT NO 1 POST ACCIDENT SAMPLING SYSTEM (PASS) - ADDITIONAL INFORMATION In a meeting held at NRC Region V on February 18, 1986, and in a subsequent telecon with the Rancho Seco Project Manager, Mr. S. Miner, on February 20, 1986, the NRC staff requested additional information with regard to the changes being made on the Rancho Seco's Post Accident Sampling System (PASS). These improvements to PASS were described in the District's February 6,1986, letter (RJR-85-60). Attachment 1 contains the requested information and is numbered to correspond to items in Attachment 1 of the February 6, 1986, letter.

It is the District's understanding that NRR does not require the backup calculational methods for estimating the radioisotope concentrations in the reactor building atmosphere and the total dissolved gases in the reactor coolant. The District discussed these calculational methods in Items 3 and 4 of Attachment 1 of the February 6, 1986, letter. On this basis, the District has deleted the calculations as backup requirements but will pursue the development of these calculational methods for inclusion into the overall PASS program plan as an aid in evaluating certain accidents. Table 1 (attached) has been updated to reflect these changes.

With regard to information on the test performed using the standard test matrix described in the NRC July 12, 1982, Clarification to Criterion 10, the District's previous attempts in 1983 to formulate the chemical constituents of the test matrix were unsuccessful. The chemicals added to obtain the concentrations called for in the undiluted test matrix precipitated out, rendering the test matrix ineffective. However, since the improvements to PASS will use on-site analysis of diluted samples, the District is purchasing chemicals to enable tests on an appropriately diluted chemical test matrix. Due to ALARA considerations, the test matrix will not include the induced gamma radiation. The District will provide this data, along with the accuracy of portions of the system affected by the PASS system modifications, to NRR as soon as it becomes available.

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-TABLE I1' '

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POST ACCIDENT SAMPLING. SYSTEM (PASS) ., + <

ORIGINAL t;URkENT BACKUP CHANGES To PASS SYSTEM '/ COtetENTS -

PASS SAMPLE SAMPLE '

DESIGN METHOD METHOD- ' - -

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Isotopic In-line In-line Off-Site

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Total' Gas In-line In-line A calculational method using a hydrogen solubility curve and RCS temp.-

and pressure is being developed for inclusion in the program plass, pH In-line In-lino Off-Site Conductivity In-line In-line Off-site Boron In-line Grab on site Off-Site The necessary lab equipment & cheinicals have been provided for on site analysis of the grab sample.

Chloride in 4-days In-line Off-site Not Reg'd The first undiluted backup grab sample will be used for off site analysis within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.

Oxygen Off-site Off-site Not Reg'd The off-site analysis'will be performed on a depressurl=ed grab sample.

t tu Ci/g to 10 Ci/g Yes Yes Yes Diluted samples will be used-for high ac'tivity on-site analysis.

3 hr & <5 rem Each Each N/A See Attachment 1 for additional information.

CONTAINMENT ATMOS.

Isotopic In-line Grab,on site Not Reg'd Bac' tup samples are not required fur on site analysis. A calculativas using isotopic mix vs R/hr graphs is being developed for the program plan. ,

Ilydrogen H Monitors H Monitors Grab on-site The baakup grab sample will be analysed on-site.

3 hr f. s5 rem Yes Yes Yes The grab samples for isotopic and hydrogen will be analyzed on-site.

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CHANGES TO RANCHO SECO POST ACCIDENT SAMPLING SYSTEM ADDITIONAL INFORMATION

1. Boron - Reactor Coolant- System (RCS) Liquid (Item II.B.3, Criterion 7)

Additional Information:

A diluted grab sample will be obtained from the existing grab sample

. taps of Post Accident Sampling System (PASS) using a portable, shielded

~ sample container.. The sample will be transported to an on-site lab for boron analysis using a laboratory quality ion chromatograph dedicated to PASS. The. ion chromatograph uses DIONEX columns with Varian eluent pumps and Wescan conductivity meters. The accuracy of the ion

' chromatograph is i 2% over the calibrated range. However, this does not include accuracy for dilution factors since data is not yet available

due to modifications in progress to improve the dilution portion of the system. With dilution, the range for boron is 12 to 4500 ppm.

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The District has performed dose rate assessments for the temporary lab facility for accident conditions. These assesments include evaluations of. both background _ and sampic. source radiation levels. The results showed that exposures to.the operators would be within the GDC-19 exposure limits.> A final dose assesment is in progress and will include input from a detailed time / motion _ study based on the new procedures.

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2. Chlorides - RCS Liquid (Item II.B.3, Criterion 5)

AdditionalInformatIon: .

u The grab sample for off-site'$ laboratory analysis , sill be an undiluted sample. On-site chloride analysis capability exists in the temporary lab used for the boron analysis' disc'ussed above. However, the District is not taking any credit for this on-site capability since sample dilution will be necessary for high activity samples which may mask ~or interfere with the chloride analysis.

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3. Radioisotopic Analysis - Reactor Building (RB) Atmosphere (Item II.B.3, Criterion 2a)

Additional Information

The District will obtain the grab sample of the RB atmosphere f rom the existing grab sample capability in the PASS using a portable, shielded sample container. The sample will be transported to an on-site lab where it will be analyzed in a laboratory quality gansna spectrometer.

The gansaa spectrometer is an intrinsic germanium element detector with a computerized gansna spectroscopy analysis system.

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The District has performed dose rate evaluations for accident conditions considering both. background and sample source radiation levels. The

. evaluations show that:the operator exposure is within the GDC-19 exposure limit. A final dose assesment for this sample.is in progress and will include input f rom a detailed time / motion study based on the new procedures.

The District's understanding.is that the. backup calculational methods for. estimating the R8 atmosphere isotopic mix is not required. However, the District intends to pursue the development of the calculational-method of determining the isotopic mix in the R8 atmosphere.-

4. -Total Gas:

lPer telecon with the NRC Project Manager for Rancho Seco on February 20, 4 1986,-the District understands that the calculational backup method for.

. determining total gas is not required. However, the District will continue to pursue developing a calculational method for estimating

-total. gas. The method being considered has changed from the February 6, 1986 submittal in that the District will use a hydrogen solubility curve and RCS pressure and temperature to estimate hydrogen / total gas.

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