ML19345G260

RO 80-008:exceeded Tech Spec 3.11.1.2 During Third & Fourth Quarters of 1980,failing to Notify Commission When Dose Requirements Limit Was Broken.Apparently Caused by Breakdown in Inter/Intradivisional Communications Sys

ML19345G260
Person / Time
Site:	Sequoyah
Issue date:	03/09/1981
From:	Green H TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
RO-80-8, NUDOCS 8103170614
Download: ML19345G260 (23)

Text

.

TENNESSEE VALLEY AUTHORITY -

CH ATTANOOG A, TENNESSEE 37401 1750 Chestnut Street Tower II March 9, 1981 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT UNIT 1 - DOCKET NO.

50-327 - FACILITY OPERATING LICENSE DPR SPECIAL REPORT 80-8 The enclosed special report provides information concerning entry into the action statements for Technical :ipecification 3.11.1.2 and 3.11.1.3.

This report is submitted in accordance with Sequoyah unit 1 Technical Specifications 3.11.1.2, 3.11.1.3, and 6.9.2.

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Very truly yours, O ,

TENNESSEE VALLEY AUTHORITY 6 7 MI\R 161981 m ~

H. J. Green D g roer . -

Director of Nuclear Power N D

% y Enclosure cc (Enclosure):

Director (3)

Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Director (40)

OfficeofInspectionandEnforcem{ent U.S. Nuclear Regulatory Commissiod Washington, D.C. 20555 k Mr. Bill Lavallee l

Nuclear Safety Analysis Center Palo Alto, California 94303 d OD) 3 NRC Inspector, NUC PR, Sequoyah I/

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SEQUOYAH NUCLEAR PLANT SPECIAL REPORT 80-8 CNIT 1 I. Summary This report provides the details concerning exceeding Technical Specification 3.11.1.2 for the last half of 1980. The report discusses the possible causes of the violation, related documentation, proposed corrective actions and conclusions.

II. Detail Discussion This section is divided into two major parts. The first part deals with TVA's organizational structure and administrative procedures as they relate to Technical Specification 3.11.1.2. Part Two of the report discusses the technical aspects of specification 3.11.1.2.

PART ONE TVA determines compliance with dose requirements of the t echnical specifi-cation through interaction of two divisions. The Division of Nuclear Power, in this case Sequoyah Nuclear Plant, samples ef fluent streams from the plant, determines the activity types and concentrations in the streams and reports this information along with effluent stream volumes to the Division of Occupational Health and Safety.

The Division of Occupational Health and Safety receives information from the plant on a monthly basis, determines compliance with the technical spec-ifications,and transmits back to the plant results of their findings. The determinations are made in accordance with the Sequoyah Offsite Dose Cal-culation Manual (ODCM).

Under normal circumstances, the information transmitted from the plant to the Division of Occupational Health and Safety and the calculated results are reported to the Commission twice a year. Should a limiting condition be exceeded, the Division of Occupational Health and Safety notifies the plant, which in turn notifies the Commission in accordance with Technical Specification reporting requirements.

On February 9,1981, plant supervisory employees were notified in writing by the Division of Occupational Health and Safety that Technical Specifi-cation 3.11.1.2 was exceeded for the third and fourth quarters of 1980.

3.11.1.2 requires that notification be made to the Cc= mission if a quarterly limit has been exceeded. This requirement was not cet for the third quarter of 1980 within the 30-day reporting period.

What apparently occurred was a breakdown in the inter / intra-divisional communications system. Plant personnel, specifically those responsible for developing and transmitting raw data to the Division of Occupational Health and Safety, were notified verbally in October 1980 that specification 3.11.1.2 possibly had been exceeded for the third quarter of 1980. Plant a

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personnel failed to realize that although a violation probably did not exist (see Part Two of this report), a special 30 day report should

. have been prepared.

As a* result of this incident, TVA will establish a firm line of communica-tions between the Division of Nuclear Power--that is, the operating nuclear plant--and the Division of Occupational Health and Safety. This communica-tion link will establish definitive reporting requirements and specific levels of management to which they shall be made.

PART TWO Technical Specification 3.11.1.2 specifies that the dose to a critical organ be limited to 5 mram/qtr and 10 mrem /yr. In the third quarter of 1980 and the fourth quarter of 1980, the effluent releases from Sequoyah Nuclear Plant for the isotope P-32 apparently caused doses of 8.0 cran and 11.9 mrem respectively.

Figure 3, attacned, shows a simplified drawing of Sequoyah's primary and secondary systems and the effluent release points from the plant. Briefly, releases from the primary coolant system are captured and held in various waste processing tanks in the auxiliary building. The waste is sampled and either processed directly to the Tennessee River or prepared for release by evaporators. For the time period in question, all radwaste releases met technical specification release limits without any prior preparation.

l There are three potential release points in the secondary coolant cycle.

( Steam generator blowdown may be directed to the river as an effluent or it may be recycled to the hotwell for cleanup in the condensate polishers and return to the steam generators. Condensate polisher regeneration vastes can be directed directly to the river or they can be directed to the turbine building sump to be diluted before return to the river. The second option is available to allow for those occasions when the regeneration wastes would exceed NPDES r quirements if sent directly to the river. The third liquid effluent discharge point in the secondary cycle is the turbine build-ing sump. This sump receives and discharges all raw cooling water wastes, the condensate polisher wastes, when so directed, and pump and valve leakages throughout the secondary cycle. Typical volumes for t':e tarbine building s;sup range from one quarter of a million gallons per day to one million gallons per day. The dose limits exceeded in the third quarter of 1980 caused by P-32 were.almost entirely due to releases from the secondary side of the

! plant;'specifically the turbine building samp and the condensate polisher regeneration vastes.: These two contributed to 98% of the. reported dose. -

If thevdose ettributed to these two release points were deleted, a limit l

would not have been exceeded.

When-the plant technical personnel were first notified of the third quarter results;"they'could not understand how the allowable dose 11mit'could have l a:

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3 been exceeded. A low concentration of P-32 had been reported for the

, month of July, 8.0 x 10-6 uci/ml. When this concentration was multiplied by the large volumes discharged by the turbine building sunp and the high reconcentration factor fo'r P-32 was applied, the dosa limit was reached.

The amount contributed by the condensate polisher regeneration wastes was relatively small compared to the turbine building sump and would not have caused the limit to be exceeded if it was the only contributor.

Technical personnel.upon learning of the potential problem, started an investigation. The investigation, however, was limited in scope until February 1981 when plant supervisors were made aware of the problem. As a result, any positive proof to discount the existence of P-32 in the -

secondary cycle during the fourth quarter and when the unit was in operation was not gathered. However, a lot of circumstantial evidence has been gathered that leadsus to believe the information for the third and fourth

! quartersof 1980, as related to the secondary cycle, was not real. Specifically:

a. We have independent analyses that verify the existence of P-32 in the primary cycle. P-32 can be formed by P-31 neutron capture. P-31 is introduced in low levels to the primary cycle by boric acid. However, we have confirmed every month since July 1980, through gamma scans, that there was no primary to secondary leakage. Therefore, we do not believe that the primary system was a source of P-32 .for the secondary system.

I

b. We have calculated, based on observed neutron levels at 90% power, that the P-32 activity, if ppb P-31 existed in the steam generator feedwater, l

wouldbe-1.27x10-2{pC1/ml. Therefore, we do not believe activation

( of P-31 is occurring in the steam generators as low levels of P-31 are maintained in an AVT chemistry plant.

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c. We have scrutinized our. laboratory practices regarding the processing i of P-32 samples. We have uncovered several deficient areas. First, the procedure required to prepare the sample for counting is highly sensitive to experience and technique. Not all employees performing the monthly P-32 procedures were properly cautioned to the sensitivity of the analyses. This is not to say they were not properly qualified. It is simply a recognition that some analysts have better technique than others. We have observed, for example, how easy it is to cross-contaminate a sample when handling more than one' type. We speculate that in July, for example, all three samples, the turbine building pump, condensate polisher, and radwaste, were contaminated when processed concurrently with spiked cross-check samples.

! l We have observed that the instrument used to count the prepared samples  !

is sensitive to outside sources. We have, for example, placed primary i i

l' coolant samples near the instrument while it was counting and observed )

a false indication. It is possible that this could have occurred on occasion.

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d. We are evaluating the use of the instrument we chose for these analyses in the range in question. A Beckman liquid scintillation detector. ~

- ModeL LS-100, is used to count the prepared samples. The instrument's calibration is excellent. We have tested it with prepared known samples,

... - we have traded samples with two other labs and we have had the factory

% representative check out the instrument. It appears, however, that the instrument may not be reliable for counting samples of very low activity.

Samples that produce counts only slightly above background must be counted for extended periods. We were unaware of this requirement until we started our investigation and talked with the Beckman appli-cations expsrts.

e. Finally, we put together a table (see Table I) to summarize the data for the third and fourth quarters for 1980, the month of January 1981, and the month of February 1981. As can be seen frcm the table, it is possible to reach different conclusions. For exampla, the December 1980 data shows no activity in the turbine building sump, yet January 1981 does. Both were months of reasonable long reactor operation periods. The November 1980 data for the condensate polisher shows more activity than the radwaste system. This hardly seems logical. As a matter of fact, none of the activity attributed to the secondary cycle seems logical and that is the problem. Until we can operate the unit again and collect new samples, we are not certain that P-32 ever existed in the secondary cycle.

III. The Offsite Dose Calculation Manual (ODCM)

The ODCM approved for Sequoyah recognizes a limited list (five) of isotopes i

that must be evaluated monthly for dose contribution. They were chosen to be l

the major isotopes of concern and consequently all other isotope activities which are reported monthly by the plant to the Division of Occupational Health

- and Safety are act evaluated for dose consideration until the end of the quarter.

Therefore, the total effect of the July 1980 data on the third quarter data was not realized until October 1980 when the quarterly analysis was performed.

IV. Support!.ve Data Tables II and III, attached, detail third and fourth quarter liquid effluent calculated doses for all activities caused by Sequoyah Nuclear Plant r eleases.

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! These tables. show that only the dose to the bone was , exceeded and that the

' major pathway was through fish. The tables are footno'ted to show the;contri-bution<dua toithe secondary cycle and radwaste.. ,

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TablesaIV and >V,-attached, detail third and fourth quarter liquid effluent

' calculated doses for fish consuar. ion alone for all. analyzed isotopes. It tshould beinoted that the only isotope of significance is P-32. The tables are footnoted to show the contribution due to the secondary cycle and radwaste.

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5 IV. Supportive Data (continued)

Appendix A, attached, details radiological impact on drinking water supplies in accordance with 10 CFR 141 reporting requirements.

Appendia B, attached, details measured radiological impact on samples of surface water, fish, and sediment.

V. Corrective Actions The following corrective actions have been or are in the process of being initiated.

a. Investigation regarding the existence of P-32 in the secondary cycle will continue following plant startup. A followup report will be prepared and sent to the Consaission within 90 days of startup.

b. Laboratory practices will be improved to minimize possibility of cross-contamination of samples during analyses and sample collection.

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

d. Use of liquid scintillation detectors as a means for detecting low levels of P-32 v111 continue.to be investigated.

e. Programs will be established to determine dose levels due to P-32 on a monthly basis. An ODCM change will be made.

f. Ccannunications between the Division of Nuclear Power and Division of Occupational Health and Safety will be strengthened.

VI. Conclusions This report does not draw any definite conclusions regarding the existence of P-32 in the secondary cycle of Sequoyah Nuclear Plant for the last half of 1980. It does, however, point out that there is enough indirect evidence to suspect that there never was any P-32 in the Sequoyah secondary cycle.

Further, the report does show through the information in Appendices A and B that the health of the public was never in danger.

As a result of the investigations into the P-32 problems for the last half of 1980, the plant and the Division of Occupational Health and Safety have done some preliminary calculations for the first two months of 1981. It now appears that the dose limits for the first quarter of 1981 will also be exceeded. In this case, however, the P-32 activity levels have b.een confirmed to exist by independent analyses and are present in the plant radwaste at sufficient levels to cause the problem. (bee Appendix C)

A report regarding the first quarter of 1981 dose limits will be made in accordance with regulatory requirements at the end of the quarter.

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SEQUOYAH NUCLEAR PLANT SPECIAL REPORT 80-8 SIMPLIFIED SKETCH OF LIQUID EFFLUENT RELEASE POINTS FIGURE I i

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s pical v To waste water Waste Secondary System Leakage to Environmentj

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SEQUOYAH NUCLEAR PIANT SPECIAL REPORT 80-8 TABLE I July August September October November December January February Month Turbine Bid. -0 ~

2.9 x 10' b Sump Act. pc/ml 8 x 10 0 0 9.6 x 10-7 4.7 x 10 0 Condensato Po11 sher -6 1.80 x 10-7 Act. pc/ml 4.9 x 10-0 0 0 2.2 x 10-6 2.2 x 10 0 1.04 x 10-6 Radwaste Act. -7 -5 pc/ml 4.2 x 10-7 3.4 x 10

-7 0 '4.9 x 10-7 1.8 x 10 2.5 x 10 -6 6.3 x 10-5 3.96 x 10 Steam Generator Blvdwn Act pc/ml 0 0 0 0 0 0 6.3 x 10-7 o 371 151 19.6 143.5 330 522 496 94.2 Hrs. Rx Critical 0 0 30 75 90 100 98

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! 0 0 274 860 1027 1156 1088 Max - MW Gen 0 y

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TABLE II e i

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. ICI AMERICA. INC IV A API 7.9E-03

8. TOTAL POPULaflOrt 005E IMAN RE18 1.?f-n1 1.11-02 9.9E-02 7.9f-03 1.2E-07 Trtms tta r a f vr a

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A. M AX IMurt 14DIVIDUAL 005E IMREMI 2.SE-05 2.4E-05 6 8E-OS 23SE-03 2.9E-03 fillMi!'.agga,LagLg1 Low SON 29E-03 .

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GI TRICT TW AUlu Islh IV. TOTAL Sut4E

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• *M NOTEI 98.11% of dose due to turbine building sump and candensate polishers P 1.98% of dose due to radwaste P

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TOTAL, bODV 5 FIN 5ii!N TUTriOLF5ir!N

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FTm:T pct,:c ';.\ ri ' 9 '!'P!/ Derm ~7FXi* FRO:! SEOD"' s RADIOLOGICAL IMPACTS ON FINISHED DRINKING WATER SUPPLIES Postulated 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 from Sequoyah Nuclear Plant in 1980 indicate compliance with the requirements

,of 40 CFR 141. The average conecatrations of beta-partic'e and photon radioactivity from u n = de radionuclides in drinking water were well below an annual dose equivalent to the total body or any internal organ of 4 milliren/ year. The attached table lists the annual dose contributed by each isotope released.

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APPENDIX A WATER INGESTION DOSES (MREM) FOR.1980 FIRST PUBLIC WATER SUPPLY DOWNSTREAM" FROM SEQUOYAH NUCLEAR PLANT l

Bone Percent Total Body Percent i H-3 2.27E-6 2.44E-6 0.3 Na-24 2.20E-6 2.20E-6 0.3 P-32 2.67E-3 44.0 1.03E-4 11.9 Cr-51 3.16E-9 2.62E-9 Mn-54 2.37E-6 2.34E-6 0.3 Fe-55 3.61E-6 0.1 5.82E-7 0.1 Fe-59 2.77E-7 2.40E-7 Co-58 1.15E-5 0.2 1.14C-5 1.3 Co-60 2.25E-6 2.24E-6 'O.3 Kr-85 0.0 0.0 Sr-89 3.89"-4 6.4 1.12E-5 1.3 Sr-90 2.98E-3 49.1 7.30E-4 84.2 Y-90 1.07E-9 2.86E-ll Zr-95 3.34E-10 7.25E-ll Nb-95 6.88E-11 2.06E-ll Tc-99m 2.43E-11 8.76E-10 -

I-131 1.63E-6 1.34E-6 0.2 I-133 5.82E-8 3.09E-8 Cs-137 7.90E-8 7.07E-8 Xe-131m 0.0 0.0 Xe-133 0.0 0.0 Xe-135 0.0 0.0 Sb-124 5,55E-3 2.19E-S Ce-144 2.00E-8 1.08E-9 ,

Pr-144 1.14E-12 5.SlE-14 W-187 2.77E-9 8.llE-10 Total 6.07E-3 99.8 8.57E-4 100.2

a. C. F. In'dustries. Inc. at Tennessee River Mile 473.

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APPENDIX B RADIOLOGICAL ANALYSES OF ENVIRONMENTAL MEDIA t

Results of radiological analyses of drinking water sources above and below Sequoyah Nuclear Plant are presented as required in radiological effluent Technical Specification 3.11.1.2. Evaluations of result,s of analyses of samples of drinking water indicate that there are no signifi-cant differences between concentrations in the upstream sources when compared to tha downstream sources. Purther, there are no significant differences between preoperational results and results from'the July to

. December 1980 time period.

Tables are attached which provide available results of analyses of samples of surface water, fish, and sediment for 1980 in the Sequoyah environs. There appear to be no radionuclide concentrations indicative of significant influence from Sequoyah Nuclear Plant operations.

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APPEND 1X B CROSS BETA _ CONCENTRATIONS IN DRINKING WATER .

SEQUOYAH NUCLEAR PIANT JULY-DECEMBER 1980

- Activity, pC1/1 Upstream Downstream Daisy Cleveland C. F. Industries Chattanooga E. I. DuPont Collection Date Dayton 8

1.2" 1.5" 0.8*8 3.0 2.1 0.9*

7-7 1.4*

8-4 2.6 1.5" 1.0 2.5 1.3"8 1.7* 0.6" 0.3*a 3.5 1.5 1.8*

eel 1.9*

9-29 2.1" 2.4 8 1.l 4.0 1.7"8 2.3" 1.5 8 8

1.9 8 2.7 1.5 1.7*

10-27 2.6 3.6 1.3 8 1.3 2.5 2.6 8 11-24 1.2" 6.1 1.4 1.0* -

3.0 2.3 12-22 Average, all data 1.510.5 1.110.5 3.010.6 1.910.5 1.610.6 Jely-Sec. 1980 2.811.6 1.910.7 2.811.4 1.410.7 1.310.7 3.611.9 2.310.4 1979 3.310.3 3.111.1 2.210.4 2.911.7 4.412.2 2.510.8 1978 for three stations 2.210.8

. . . for July-Dec. 1980: 1.811.2 Average. Values >LLD only-4.111.8 2.4 < LLD 3.010.6 2.6 2.6 July-Dec. 1980 2.710.2 2.710.4 1979 3.611.2 2.4 2.4 4.011.8 2.610.1 3.511.4 4.812.1 3.210.5 3.310.3

+

1978 3.611.0 for three stations

'. -t for July-Dec. 1980: 3.711.7 2.910.5

a. Value reported is less than the nominal lower limit of detection (LLD) of 2.4 pCi/1.

b. Uncertainty reported is one standard deviation.

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APPENDIX B .

CROSS ALPHA AND BETA CONCENTRATIONS IN SURFACE WATER ,

SEQUOYAH NUCLEAR PLANT JULY-DECEMBER 1980 .

• Activity, pCi/1 Upstream ,

Downstream

-TRM 497.0 TRM 483.4 TRM 473.2 Collection Date .a- 8- G B a _ 6

-0,7 a,b c -0.6 a,b 1,9 c 7j7 d.5 'a,b 1,9c 2.0

-0.5 a,b 2.lc **b C d

-0.5 a,b 1.5C -0.6 a,b 1.5 C -0.8 1.5 31 .

1.1c d 0.6 a a,b 1,9 c 1.9 -0.1 a,b 1,9 c -0.2 28 198 1.5 a 2.lc 8 3.1 8/28d 3.7 2.5 1.7 3.8 4.0 9/26 d 1.3 a 3.6 9/26 1.8c 3.4 4.2 2.3 3.0 10/22 2.1 9.3 3.8 8 10/22d 6.8 0.9 a 2.3 c 0.0 3.6 11/21 3.6 0.0

• 3.0 1.1 a 2.7 3.4 5.4 12/19 Average, all data 8 2.611.5 1.111.8 3.0t1.5 0.711.8 2.610.8 July-Dec. 1980 2.0 1 2.7 0.911.1 3.613.0 0.710.6 4.613.0 0.413.0 2.411.0 1979 0.410.7 3.411.5 0.710.6 3.711.3 0.810.9 4.814.1 1978 Average: Values >LLD only Ju[y-Dec. 1980 4.713.2 3.911.7 3.410.0 4.510.8. 3.211.2 3.210.3 3.6 5.413.4 <LLD 5.413.0 <LLD 3.110.9 1979 6.914.0

<LLD 3.811.5 <LLD 3.911.3 3.0

. 4 1978

a. Value reported is less than the nominal lower limit of detection (LLD) of 2.0 pC1/1,

b. Negative value is an artifact of counting statistics and does not infer a negative activity.

c .' Value reported .fa less than the nominal LLD of 2.4 pCi/1.

d. Replicate sample.

e. Uncertainty reported is one standard deviation.

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APPENDIX B .

CONCENTRATIONS _OF RADIOACTIVITY IN FISH .

SEQUOYAH NUCLEAR PLANT APRIL-MAY 1980 ,

Sampling Activity, pCi/a. dry weight Location Cross Cross I87 Cs "8

'8 Sr K a 8 esSr Species (Reservoir) 0.1 0.1 0.5 0.1 0.02 -

LLD -

8 0.9 27.2 0.8 0.1 0.15 14.5 White Crappie Watts Bar 0.09 17.1 Chickamauga 0.5 25.4 0.2 0.1 (Flesh) b 0.14 15.5 i Nickajack 1.6 15.1 -1.0 0.3 1.0 ' 0.2 2 -0.4 0.2 0.12 16.3 Average a 0.5 10.8 0,2 0.0 0.14 10.3 Channel Catfish Watts Bar 0.06 13.7 Chickamauga 1.0 16.3 0.0 0.0 (Flesh) 0.9 27.6 1.6 0.0 0.03 12.4 Nickajack 1.0 22.0 0.8 0.0 0.05 13.0 Averagee Smallmouth 0.4 0.0 0.07 17.0 Buffalo Watts Bar a 1.9 14.7 1.1 15.3 0.l 0.0 0.06 11.4 (Flesh) Chickamauga b 15.3 0.8 16.8 -1.2 0.0 0.07 Nickajack c 1.0 16.0 -0.6 0.0 0.06 13.4 Average Smallmouth i 9.2 0.2 b 0.2 0.12 7.9

' ' ' ' I Watts Bar" 1.1 Buffalo 0.5 14.2 -0.1 0.1 0.04 6.7 (Whole) Chickamauga 9.8 Nickaja'ck 1.3 28.5 0.4 ' O.0' ND e 0.9 21.4 0.2 0.1 0.02 8.2 Average

a. Upstream impoundment.

b. Negative value is an artifact of counting statistics and does not infer a negative activity.

c. Average of results from downstream impoundment. ,

LLD-Lower limit of detection. -

ND -No activity detected.

i s '. ; ,

APPENDIX B  ! _

a, . .

CROSS ALPHA AND BETA CONCENTRATIONS IN SEDIMENT ~

. SEQUOYAH NUCLEAR PLANT

. JULY-DECEMBER 1980 Activity, pCi/g. dry weight Date Upstream Downstream Collected TRM 472.8 TRM 483.4 TRH 480.8 TRH _496.5 a S a 8 a 8 a 8 3.8 29.4 2.1 20.3 3.6 21.6 2.4 19.4 -

g 8/14 ,,

12.5 3. 4 ' 26.6 3.0 20.0 3' .

11/18-21 2.8 13.1 1.7 -

. p :.

1.910.3 16.415.5 3.510.1 24.113.5 2.710.4 19.710.4 Q.

Average: 3.3 0.7 8 21.3111.5 s- '

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Shoreline Stations i TRM 477 TRM 485 TRM 478.2 a 8 a 8 a 1 8/28 1.3 9.3 1.2 3.0 1.9 6.3 9

a. Uncertainty reported is one standard deviation.

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APPENDIX B RADI0 ACTIVITY LN FISH SEQUOYAH NUCLEAR PLANT NOVEMBER-DECEMBER 1980 Sampling Location Species (Reservoir) Activity pCi/g. dry weight 137 Cs 40g White Crappie Watts Bar* 0.18 19.0 (Flesh) Chickamauga 0.10 17.4 Nickajack O.08 16.8 Averageb 0.09 17.1 Channel Catfish Watts Bar* 0.11 16.4 (Flesh) Chickm=muga 0.04 12.1 Nickajack 0.02 12.6 Averageb 0.03 12.4 Smallmcuth Buffalo Watts Bar* 0.03 11.5 (Flesh) Chickamauga 0.05 11.4 Nickajack O.03 9.5 b 10.4 Average 0.04 Smallmouth Buffalo Watts Bar a 0.02 7.4 (Whole) Chickamauga 0.03 6.3 Nickaj ack O.01 6.9 Averagab 0.02 6.6 I

l a-Upstream impoundment.

b-Average of results from downstream impoundsents.

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APPENDIX C SPECIAL REPORT 80-8

1.

SUMMARY

This appendix raports details of exceeding limiting condition for operation (LCO) 3.11.1.3.

The report identifies the cause of the problem, the corrective action taken, and the action taken to prevent recurrence.

II. DETAIL DISCUSSION Technical Specification 3.11.1.3 states "The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid affluent from the site when averaged over 31 days would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.*"

It could be interpreted that Sequoyah exceeded these limits for the last half of 1980. Hocever, the Sequoyah design does not permit processing.of turbine building sump discharges.and in light of the facts brought forth in the other portions of this report, it is unlikely that processing was required.

When the P-32 problem was brought to management's attention, an l

investigation was started that revealed the subject LCO was exceeded

' for the months of Jcnuary,1981 and February,1981. This infor-mation would technically not have been available until the end of the first quarter of 1981. But as more information was made i

l available to the plant staff, specifically the high re-concentration

! factor applied to P-32, it seemed prudent to do an early evaluation.

The evaluation concluded that the LCO limits would be exceeded because sufficient volumes of primary system water were discharged without processing. These discharges were previously made using only the five isotopes mentioned in the ODCM as source terms for calculating release concentrations. Using this methodology, limits were well below allowable technical specification values for dose and 10 CFR 20, Appendix I release concentrativas, (Refer to Sequoyah Monthly NRC Reports for effluent release values)

Prior to February, 1981, Sequoyah elected not to use its design installed waste evaporators. There were three reasons for this.

First, the activity levels up until January, 1981 were so low that processing even from an ALARA standpoint was not reasonable. Secondly.

Sequoyah like all other Westinghouse-designed plants has had numerous problems with its evaporators. However, even though the evaporators

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2 were marginal they could and would have been operated if needed.

Thirdly. Sequoysh has elected to use an outside vendor to process evaporator bottoms and spent resins. Due to problems with the vendor contracted, previously reported to the Commission, Sequoyah avoided use of the evaporators.

• During the fall of 1980 when it became evident that the installed evaporators would not be economical to operate, TVA proceeded to purchase the services of a vendor to demineralize radsaste.

This system was projected for installation around January,1981.

Due to slippages in schedule, it finally was installed and started operation in February,1981. Until the demineralizer was installed and af ter learning of the P-32 problem, no radwaste was discharged from Sequoyah.

All future radwaste releases will be either processed through a demineralizer or by a new waste evaporator which is nearing completion.

III. CONCLUSIONS Sequoyah anticipates no further violations of this limit due to P-32 or other-isotopes. ODCM changes will be made to evaluate P-32 on a monthly basis and all future radwaste releases will be processed. .

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U.S. NUCLEAR REGULATORY COMMIS5nJN NRC FORM 366 am .

LICENSEE EVENT REPORT CONTROL BLOCK: l l j l l l l (PLEASE PAINT OR TYPE ALL REQUIRED INFORMATION) 1 6 10111 I I I I I I l@l 14 1S l I I I I LICENSE NUMBER I I I I I l@l26 2S l l 1 l LICENSE TYPE 40

!@lST CAT I

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7 8 9 LICENSEE CODE CON'T IT m8 aga; i Gioisi 0101013 l'J.i?Gita ieill 68 69 EVENT DATE i Git i /101110171@

74 75 REPORT DATE 80 7 60 61 DOCKET NUMSER EVENT OESCRIPTION AND PROBABLE CONSEQUENCES h

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LE Rr RO EVENT YEAR E l l J qg E 27 28 29 30 J1 32

_ 21 22 23 24 26 HOURS S8 i FOR B. SUPPL P MANUFAC RER N AC ON O P NT i i@i34 i@ i i@ i I@ i i  ! i i LJ@

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l1 l6l l l l l l l l PERSONNEL EXPOS ES NOVBER DESCRIPTION i

n oii i i l@i~/YPE@i l PERSONNEL INJURIES NOVSER CESCRIPTION I

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