ML20004D763

Special Rept 81-03 Re Radioactive Releases for Quarter Ending 810331 & Supplemental Info to Special Rept 80-08 on Radioactive Releases for 3rd & 4th quarters,1980

ML20004D763
Person / Time
Site:	Sequoyah
Issue date:	05/29/1981
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20004D761	List: ML20004D760 ML20004D763
References
81-3, NUDOCS 8106090739
Download: ML20004D763 (10)

Text

__ _._

e t

.{s_ ;

SEQUOfAH NUCLEAR PLANT SPECIAL REPORT 81-3 UNIT 1 I. Summary This report provides the details of exceeding Technical Speci-fication 3.11.1.2 for the first quarter of 1981 and provides supplemental information to Special Report 80-8. The report discusses the cause of the first quarter 1981 violation and corrective actions taken.

II. Cetailed Discussion This section is divided into two major parts. The first part details the first quarter 1981 violation, and the second part provides the supplemental information for Special Report 80-8.

PART ONE Special Report 80-8, Appendix C, alerted the Commission to the probability that Technical Specification 3.11.1.2 would be exceeded for the first quarter of 1981. It was pointed out that sufficient volumes of primary water were released without processing and that these volumes would cause the hypothetical

• quarterly doses to be exceeded. The releases were made in January and February 1981 prior to the realization that P-32 was a dose problem. A determination of whether the limit actually was exceeded could not be made until the end of the quarter when all subsequent releases became known and river dilution effects could be applied. Those effects were applied in April and the calculations determined that the hypothetical dose for the first quarter of 1981 was 28 mrem organ (bone) via the fish pathway. The calculations show that 99 percent of the dose was due to P-32. The allowable organ quarterly

• limit is 5 mrem and the yearly limit is 10 mrem.

Beginning in February, all radwaste releases at Sequoyah have been processed through portable demineralizers. The maximum organ bone dose for Sequoyah for the months for March and April, including that attributed to P-32, was calculated to be hypothetically 0.4 mrem and 0.78 mrem respectively. These monthly values are below that which would be necessary to exceed quarterly and yearly limits. Therefore, it is antici-pated that no further violations will occur.

810 6 09 01P3h)

W"-

i y~. - _ _

s- .

PART TWO Special Report 80-8 informed the Commission of suspected violations to Technical Specification 3 11.1.2 for the third and fourth qua- cers of 1980. The report provided data which indicated V ac P-32 activity was present in the secondary cycle dn'ing the third and fourth quarters of 1980 and the first ;wo months of 1981. The data, however, was suspect for a number of reasons as was pointed out in the report.

One of the corrective actions committed to in the report was a followup investigation of the existence of P-32 in the l secondary cycle. That investigation has been concluded with a determination that for the months of March and April when the unit operated for 15 days and 24 days respectively at or near 100% power, no P-32 activity could be detected in the  ;

secondary cycle. Therefore, we feel confident that the values ,

reported for the third and fourth quarters of 1980 and the first two months of 1981 were, in fact, analytical errors and that the Technical Specification limits were never exceeded.

Other .orrective actions and their status listed in Special Report 80-8 are as follows:

a. Laboratory practices will be improved to cinimize the  ;

possibility of cross-contamination of samples during l analyses and sample collection.

Separate locations have been established for storage of primary and secondary samples. Procedures have been revised to ensure that sample preparation and counting of primary and secondary samples are done separately.

b. Increased sample volumes will be tried in an attempt l to improve activity concentrations and therefore reduce counting errors.  ;

This item has been determined to be unnecessary,

c. Use of liquid scintillation detectors as a means for detecting low levels of P-32 will continue to be investigated. l This item is still active but preliminary results indicate that the overall method is acceptable.

We are continuing to work with new procedures to find the best one for ou r applications.

d. Programs will be established to determine dose levels i due to P-32 on a monthly basis. An Offsite Dose Calculations ,

Manual (ODCM) change will be made.

Completed. -

l 1

4 L

P PART TWO (Continued) ,

e. Communications between the Division of Nuclear Power  ;

I and the Division of Occupational Health and Safety will be strengthened.

Completed.

III. Supportive Data Appendix A, attached, details radiological Lapact on drinking water supplies in accordance with 10 CFR 141 reporting requirements.

L Appenoix B, attached, details measured radiological impact on -

samples of surface water above and below Sequoyah in accor-dance with 10 CFR 141 reporting requirements.

i Appendix C, attached, shows calculated doses for the past four ,

quarters from releases from Sequoyah Nuclear Plant.

Table I, attached, summarizes P-32 release activity data for  !

the first four months at Sequoyah as related to unit 1 operation.

IV . Conclusions and Recommendations

, Sequoyah did exceed the allowable offsite dose limit for the first quarter of 1981 due to the isotope P-32. However, it has subsequently started processing radwa te to eliminate the problem. Sequoyah did not exceed the allowable limit for the third and fourth quarters of 1980 as previously reported.

Sequoyah is presently processing all radwaste through portable  !

deminerali.:ers, primarily to reduce the dose effect of P-32.

If P-32 were not a consideration, releases could be made, in t some instances, without processing at all. The Commission has i data that indicates the effects of P-32may not be as impacting as originally thought. NUREG/CR 1336 states that the bioac-cumulation factor in freshwater fish for P-32 could be as low i as 3000 ues/sm/uci/ml vice 100,000 uci/sm/uci/ml as per Regulatory Guide 1.109.

TVA strongly recommends that the Commission consider a change _

I to Regulatory Guide 1.109 based on the latest available infor-mation. Such a change would be in the best interest of the utilities, who are trying to run as efficiently as possible, and would incur undue costs by having to unnecessarily process radwaste. It would also benefit the public who would be  ;

unduly alarmed by fictitious reports of activity releases and s have to eventually pay for the excess processing costs.

l l

J i

APPEND L.( A RADIOLOGICAL IMPACTS ON FINISHED DRINKING WATER SUPPLIES Pesculated radiological impacts on finished drinking water supplies have been evaluated as required in Radiological Effluent Technical Specification 3.11.1.2. Calculations based on reported effluent releases L from Sequoyah Nuclear Plant for 12 months ending in March 1981 indicate compliance with the requirements of 40 CFR 141. The average concentrations of beta-particle and photon radioactivity from manmade radionuclides in drinking water were well below an annual dose equivalent to the total body l or any internal organ of 4 millirem / year. The attached table lists the -

annual dose contributed by each isotope released.

P 9

b

(

I i

i s

r i.m. , 't - -y-ia wimrdt'.grPr 5

, . m 4

APPENDIX A ANNUAL WATER INCESTION DOSE (mrem) 'THROUCH MARCH 1981 AT QFST PUBLIC WATER SUPPLY DOWNSEEAM" FROM SEOUOYAll NUCLEAR PLANT Bone Percent Total Body Percent H-3 9.33 E-5 u.6 .1.00 E-4 6.0 Na-24 2.25 E-6 . 2.25 E-6 0.1 P-32. 1.10 E-2 73.3 4.23~E-4 25.3 Cr 3.91 E-7 3.23 E-7 lin -54 5.57 E-5 0.4 5.46 E-5 3.3 Fe-55 4.47 E-6 7.21 E-7 Fe-59 3.26 E-5 -

0.2 2.92 E-5 1.8 Co-58 2.66 E-4 1. 8 - 2.64 E-4 15.8 Co-60 3.68 E-5 0.2 3.67 E-5 2.2 Zn-65 2.68 E-7 3.88 E-7 Kr-85 0.00 0.00 Sr-89 4.97 E-4 3.3 1.43 E-5 0.9 -

Sr-90 2.98 E-3 19.9 7.30 E-4 43.7 Y-90 1.07 E-9 2.86 E-11 Zr-95 2.47 E-7 5.36 E-8 Nb-95 5.16 E-8 1.54 E-8 Tc-99m 2.43 E-11 8.76 E-10 Sb-124 5.55 E-8 2.19 E-8 I-131 9.38 E-6 7.69 E-5 0.5 I-133 1.77 E-7 9.32 E-8

• Xe-131m *0.00 0.00 Xe-133 0.00 0.00 Xe-135 0.00 . 0.00 Cs-137 6.17 E-7 5.15 E-7 Ba-140 5.05 E-5 0.3 3.33 E-6 0.2 La-140 6.68 E-9 -

8.90 E-10 cc.144 1.88 E-6 1.01 E-7 '

Pr-144 1.16 E-10 5.89 E-12 W-187 3.28 E-8 9.54 E-9 Total- 1.,50 E-2" 100.0 1.67 E-3 99.8

a. C. F. Industries, Inc. at Tennessee River Mile 473. .

b. 9.33 E-5 = 9.33x105

c. -60% of this dose is attributable to releases during the first quarter of 1981.

l I

l l

A _

APPENDIX B RADIOLOGICAL ANALYSES OF ENVIRONMENTAL MEDIA Results of radiological analyses of drinking water sources above and below Sequoyah Nuclear Plant are presented for the first quarter of 1981 as required in Radiological Effluent Technical Specification 3.11.1.2. Evaluations of results of analyses of samples of drinking water indicate that there were no significant differences between concentrations in the upstream socaces when compared to the downstream sources.

A table is attached which provides available results of analyses of samples of surface water for 1981 in the Sequoyah environs. There appear to be no radionuclide concentrations indicative of significant influence from Sequoyah Nuclear Plant operations.

Environmental data for 1980 have been provided to the NRC via the attached annual monitoring report for the Sequoyah Nuclear Plant.

4

~

• RADIOACTIVITY IN DRINKING WATER SlfPPLIES SQN IST QUARTER 1981 Activity. oCi/1 Sampling Location Sampling Date Cross S Camma Emitting Radionuclides 8[ asSr Sr ND ND ND ND Soddy-Daisy, TN 1/20/81 ND Soddy Creek mile 0.5 2/17/81 2.110.6, 8.6 miles upstream 3/17/81 ND ND Quarterly Corposite ND ND r

Dayton, TN 1/20/81 2.910.7 ND TRM-503.8 2/17/81 4.910.8 ND 20.2 miles upstream 3/17/81 2.610.7 ND Quarterly Composite 301154' ND ND Cleveland TN 1/20/81 ND ND Hiwassee diver 22.9 miles 2/17/81 2.110.6 ND 19.2 miles upstream 3/17/81 ND ND Quarterly Composite ND ND ND C. F. Industries 1/29/81 2.510.7 ND TRM-473.0 2/13/81 4.110.9 ND 10.6 miles downstream 3/16/81 5.710.9 ND Quarterly Composite 273t54 ND ND E. I. Dupont 1/20/81 2.610.6 1:D TRM-470.5 2/17/81 1.610.6 'ND 13.1 miles downstream 3/17/81 3.110.6 HD ND ND ND Quarterly Composite Chattanooga, TN 1/20/81 2.510.6 ND TRM-465.3 2/17/81 2.610.6 ND 18.3 miles downstream 3/17/81 3.310.6 ND Quarterly Composite ND ND ND

a. The uncertainty reported in the 1-sigma counting error.

ND- No activity detected above the lower limit of detection (LLD).

Note: All drinking water samples collected on 2/17/816 2/18/81 were analysed for 8*P. No 3*P activity was detected in th.

s a mo l .s e. ,

^

s.

3 RADIOACTIVITY IN SURFACE WATER SQN.

IST QUARTER 1981 Activity, pC1/1 Gamma Emitting Radionuclides JH. esSr Sodr Sampling Date Gross

• Cross B Sampling Location _ _

2.420.7" ND 1/19/81 ND

. TRM 497.0 ND 7.511.1 ND (upstream) 2/13/81' ND 3/16/81 ND 5.110.8 402158- ND .ND Quarterly Composite .j .

3.711.1 ND 1/19/81 ND TRH 483.4 ND 6.310.9 ND (downstream) 2/13/81 ND 3/16/81 ND 4.610.9 ** 307154 ND ND Quarterly Composite 2.6 0.7 ND 1/19/81 2.010.9 TRM 473.2 3.911.6 8.211.0 ND '

(downstream) 2/13/81 ND 3/16/81 ND 5.920.8 330155 ND ND Quarterly Composite q a. The uncertainty reported is the 1-sigma counting error.

ND- No activity detected above the lower limit of detection (LLD). s2 P. No s2 P activity was detected in these sampieg

Note: All surface water sampics collected on 2/13/81 were analyzed for d

i

)

d

. _ . . g - .,m -.. - - - ,m ., m. .- - , , ,_..me . - . . , - . - - -,-

APPENDIX C 4

CALCULATED DOSES (mrem) FOR 12 CONSECUTIVE MONTHS FROM RELEASES FROM SEQUOYAH NUCLEAR PLANT _

i TOTAL BODY ORGAN (BONE) i Releases to Releases to Liquid Releases Atmosphere Liquid Releases Atmosphere _ r

-1 -2

-2 2.2x10 0.0 5.2x10 1.9x10  !

Second Quarter 1980 0

-1 -2 3.5x10 1.1x10 9.1x10 0.0 Third Quarter 1980- -1 1 -1

-1 5.3x10 1.2x10 1.4x10 1.7x10 Fourth Quarter 1980 1 -1 0 -1 1.1x10 2.6x10 2.8x10 2.7x10 First Quarter 1981 TOTAL BODY ORGAN (BONE)_

- 12 month total for 52 all releases 2.4 Note: There was no identified direct radiation exposure to individuals offsite resultant from plant operations.

-Approximately 98% of the. Organ dose is due to P: ."32.

)

i

[

b wm  % .. ..- m -

0-g TABLE I SEQUOYAH NUCLEAR PLANT PHOSPHORUS 32 RELEASED RELATIVE TO THE OPERATICN OF UNIT l' Month Jan!!ry Fekbkry Mk!k kphk1 Turbine Bld.

Sump Act. C1 1.9x10-2 0 0 0 Condensate Polisher .

Act. Ci 5.08x10-3 1.98x10-3 0 0 l Radwaste Act. -2 C1 1.4x10-1 4.55x10 2.08x10-3 3.15x10-3 Steam Generator Blvdwn Act Ci 8.85x10 O O O Hrs. Rx Critical 496 94.2 336 576

% Max PWR 100 98 100 100 6

Max - MW Cen 1156 1088 1088 1132 i

%.