BSEP-82-2778, Responds to NRC Re Violations Noted in IE Insp Repts 50-324/82-40 & 50-325/82-40.Corrective Actions: Perchloric Acid Pretreatment Step Successfully Demonstrated to Eliminate Organic Interferences

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Responds to NRC Re Violations Noted in IE Insp Repts 50-324/82-40 & 50-325/82-40.Corrective Actions: Perchloric Acid Pretreatment Step Successfully Demonstrated to Eliminate Organic Interferences
ML20070M437
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 12/22/1982
From: Dietz C
CAROLINA POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
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ML20070M429 List:
References
BSEP-82-2778, NUDOCS 8301250204
Download: ML20070M437 (3)


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P1 0 3 Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 December 22, 1982 FILE:

B09-13510E SERIAL: BSEP/82-2778 Mr. James P. O'Reilly, Director U. 3. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street N.W.

Atlanta, GA 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1&2 LICENSE NOS. DPR-71 AND DPR-62 DOCKET NOS. 50-325 AND 50-324 SUPPLEMENTAL RESPONSE TO INFRACTIONS OF NRC REQUIREMENTS

Dear Mr. O'Reilly:

The Brunswick Steam Electric Plant's (BSEP) response to IE Inspection Report 50-324/82-40 and 50-325/82-40, dated December 2, 1982, failed to include the table addressed in that response. Additionally, the date for full compliance has been revised to December 31, 1982. The response to that report is included herein in its entirety.

Violation:

(Security Level V)

Technical Specification 3.5.1.C of Appendix B requires that sampling and t

l analyses of liquid radioactive waste shall be performed in accordance with Table 3.5-1.

Contrary to the above, analyses of liquid radioactive waste ;ere not performed l

in accordance with Table 3.5-1 in that the monthly composite si mples for l

July 1981, February 1982, April 1982, July 1982, and August 1962 did not meet j

the required minimum detectable concentration for Sr-89.

In addition, the composite sample analysis for Sr-90 did not meet the minimum detectable concentration for February 1982 and August 1982.

Carolina Power and Light Company's Response Carolina Power and Light Company acknowledges that the failure to meet the minimum detectable concentration for Sr-89 and Sr-90 is a violation of NRC requirements. The inspector noted that Technical Specification Table 3.5-1

-8 requires minimum detectabic activity (MDA) of 5.0 X 10 pCi/ml for Sr-89 and Sr-90 analysis on the monthly radwaste liquid composite release samples.

After review of the situation, other problem areas were discovered and are reported on Table _1.

r" l r301250204 830103 PDR ADOCK 05000324 g

PDR_ _

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Mr. James P. O'Reilly December 22, 1982 Analysis for Sr-89 and Sr-90 are performed for BSEP by the Harris Energy.and.

Environmental Center (HEEC) which is a corporate support facility. The HEEC reporting form does not indicate the BSEP technical specification requirements and thus comparison reviews were not adequate. The analysis difficulties were due to organic interferences from chelating and sequestering agents which are normally released from the plant detergent drain tanks. The composition of the release composite sample varies from month to month causing the severity of these interferences to fluctuate. These organic interferences have caused low yields in the strontium separation procedures which have resulted in higher than acceptable MDA values.

Corrective action has been initiated. A perchloric acid pretreatment step has been successfully demonstrated to eliminate the organic interferences and has resulted in acceptably high strontium separation yields ranging from 40% to 80%. Also, during the course of the chemical separation, the atomic absorp-tion unit is being utilized to monitor the strontium carrier concentration to avoid sample loss.

Additional corrective actions include:

1.

Revision of the HEEC report form to present BSEP technical specification required MDA values such that review is performed at every level through which the report travels.

2.

The HEEC report will be routed to plant QA for review.

3.

HEEC Sr-89 and Sr-90 chemical separation and activity calculation procedures will be revised to accommodate thorough review of all pertinent results.

4.

BSEP E&RC procedure 1000, Sampling and Analysis Schedule for Radioactive and Nonradioactive Chemistry, has been revised to accommodate monthly liquid and gaseous composite samples. This revision will allow constant review by both management and the technicians.

5.

BSEP E&RC procedure 1000 will be routed to QA for review on a monthly basis after completion.

i HEEC and BSEP are in the process of rraking changes to all phases of the current methods. This process will require many computer software and proce-l dural administrative changes; therefore, the corrective actions will not be j

completed until December 31, 1982.

Samples will be collected in the interim as required and analyzed in accordance with approved procedures.

Very truly yours, R. Dietz, General Manager l

Brunswick Steam Electric Plant RMP/CER/gvc/LETGC3 cc:

Mr. R. C. DeYoung J

n-TABLE 1 Dates (Month, Year)

Sr-89 (MDA) uci/ml Sr-90 (MDA) uci/ml

  • August 1982 3.0E-7
  • 1.9E-7
  • July 1982 8.8E-8 N/A April 1982 7.5E-8 N/A
  • February 1982 2.5E-6
  • 1.4E-6 October 1981 2.02E-6 7.08E-7
  • July 1981 1.32E-7 N/A May 1981 1.04E-7 March 1981 7.81E-8 October 1980 5.81E-8 August 1980 5.41E-8 October 1979 3.72E-7 August 1979 6.69E-8 February 1979 5.10E-8 bay 1977 1.22E-4 3.5E-5 March 1977 9.62E-8 N/A February 1977 1.67E-7 5.90E-8
  • Records reviewed and dates cited by NRC Inspector in Report Nos. 50-325/82-40 and 50-324/82-40; Item 7 Note: Other dates listed above were discovered by BSEP personnel during an investigation follow up.

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