ML19350C187

Special Rept 80-8:during Third & Fourth Quarters of 1980, Tech Spec 3.11.1.2 Found Exceeded.Caused by Effluent Releases of P-32 from Facility.Investigation of P-32 in Secondary Cycle Will Continue Following Plant Startup

ML19350C187
Person / Time
Site:	Sequoyah
Issue date:	03/24/1981
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19350C185	List: ML19350C184 ML19350C187 ML19350C189 ML19350C190
References
RO-80-8, NUDOCS 8103310483
Download: ML19350C187 (21)

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SECT 0YAH NUCLE.AR PLN.~T SPECIAL RE?CRT $0-8 CNIT 1

1. Su==a ry This report prevides the details concer:4=; exceeding Technical Specifica:1cn

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3.11.1.2 for the last half of 1950. The reper: discusses :he pessible causes of the viola:icn, related decumentaticn, picpesed cc rective actions and conclusiens.

l!. Detail Discussicn This sectica is divided in:c two major parts. The firs: par: deals with TVA's organicatienal structure and administrative procedures as they relate to Technical Specifica:ica 2.11.1.2. Par: Two of the reper: discusses :he

-technical aspects of specifie:tien 3.11.1.2.

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. PART CNI TVA dete::ines cc=pliance with dose requirenents cf the t echnical specifi-catica through interacticn cf tue divisices. The Divisien of Nuclear Pever.

in this case Sequoyah Nuclear Plant, samples ef fluent streams frr: the plant, deter =ines the activity types and concentratiens in the streams and repcrts this infer:atica alcng~ vi:h effluent strea: volumes :o the Division of Occupational Eealth and Saf ety.

The Division cf Occupatienal Health and Safety receives infer:ation frc= the plant on a =cnthly basis, deter ines cc pliance with the :echnical spec-ificaticas,anc trans=1:s back to the plant results cf their findL=gs. The deter =inations are made in accc dance with the Sequcyah Offsite Oose Cal-culatien Manual (CDCM) .

Under nor:al circu= stances. .the inf er:aticn trans=1::ed f c: the plant to the Divisica of Ocuupational Health and Safety and the calculs:ed results-~

are repcreed to the Cc==1ssien twice a year. Should a li iting cceditien be exceeded, the Divisten cf Occupatienal Health and Saf ety notif aes Obe

plant, which in turn notifies the Cc==1ssica in acccedance with Technical Specifica:ica reporting require =ents. -

On February 9,1981, plant supervisory empicyees were notified in writing by the Divisien of Occupational Health and. Safety that Technical Epecifi- - '

cation 3.11.1.2 was exceeded for the third and four:h quar:ers of 19E0.

- 3.11.1.2 requires that notificatien be made :c the Cc :issien if a quarterly li=it has been exceeded. This requirement was no: et for the third

. quarter of 19S0 within the 30-day reporting period.

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<What apparently eccurred vas a breakdev: in the inter / intra-divisional cc==unicaticas syste . Plant persennel.. specifically these respensible

.1for developing and trans=1::ing rav data to the Divisica cf Occupaticnal

. Eealth and Safety, we're notified verbally in Oc:cher 1950 that specifica:icn 3.11.1.2 pessibly had been exceeded fer the :hird quarter of 19E0. Plant

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O personnel failed to reali:e that although a violation prcbably did not exist (see Part Two of this report), a special 30 day report should have been prepared.

As a result cf this incident, TVA will establish a firs line of cer=unica-tions between the Division of Nuclear Pcwer--that is, the operating nuclear plant--and the Division of Occupaticnal Health and Safety. This con =anica-tien link will establish definitive reporting require =ents and specific levels of =anagenent to which they shall be made. .

PART TW Technical Specification 3.11.1.2 specifies that the dose to a critical organ be limited to 5 =re=/qtr and 10 =res/yr, In the third quarter of 1960 and the fourth quarter of 19E0, the effluent releases frem Sequoyah Nuclear Plant for the isotope P-32 apparently caused doses of S.O arem and 11.9 mrem respectively.

Figure 1, attached, shows a si=plified drawing of Sequoyah's pri=ary and

. secondary systems and' the af fluent release points frc= the plant. Briefly, releases frem the primary ecolant system are captured and held in varicus waste processing tanks in the auxiliary building. The vaste is sampled and either processed directly to the Tennessee River or prepared for release

by evaporators.~ For the time period in question, all 'radvaste releases met cachnical' specification release limits withcut any prior preparation.

. There are three' potential release points in the secendary ecolant cycle.

Steam generator blowdevn say be directed to the river as an effluent er it nay be recycled to the hotwell for cleanup in the ccedensate polishers and return to the steam generators. Condensate polisher regeneratica 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 optica is available to allow for those occasiens when the regeneratica vastes would exceed NPDES requirements.if sent directly tg the river. The third liquid effluent. discharge point in the seccadary cycle is the turbine build- -

ing sump. This sump receives and discharges all raw coeling water vastes, the condensate polisher vastes, when so directed, and pump and valve leakages

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throughout the secondary cycle. - Typical volumes for the' carbine building samp

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range from one quarter of a million gallons per day to one millien gallens

, 'per day. The dose limits exceeded in'the third quarter of 1980 caused by P-32 'were al=ost entirely due to releases frem the secondary side of the

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plant, specifically the~ turbine building samp and the cendensate polisher regeneration vastes.. These two centributed to 98% of the reported dose.

. If the. dose attributed to these two release points were deleted, a' limit

-would not- have been exceeded.

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' Shen the plant technical personnel were first notified of the third quarter

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results, they could not understand how the allcwable dose li=it could have

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3 been exceeded. A lew concentration of P-32 had been repcrted for the

=onth of July, 8.0 x 10-6 pei/=1. When this ecocentration was =ultiplied by the large volu=es discharged by the turbine building su=p and the high reconcentratien factor for P-32 was applied, the dose li=1c was reached.

The a=ount centributed by the condensate polisher regeneration vastes was relatively s=all cc= pared to the turbine building su=p cad wculd not have caused the li=it to be exceeded if it was the cnly centributor.

Technical personnel.upon learning of the potential prcblem, started an investigatien. The investigation, however, was 11=ited in scope until

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February 1981 when plant supervisors were =ade aware of the prcble=. As a result, any positive prcof to disecunt the existence of P-32 in the secondary cycle during the fourth quarter and when the unit was in operatica was not gathered. However, a lot of circu=scantial evidence has been gathered that leadsus to believe the infor:ation 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 pri=ary cycle. P-32 can be for=ed by P-31 neutren capture. P-31 is introduced in low levels to the pri=ary cycle by boric acid. Hewever, we have confir=ed every =ench since July 1980, through gn==a scans, ,

that there was no pri=ary to secendary leakage. Therefore, we do not believe that the pri=ary systa= vas a source of P-32 for the secondary syste=.

.b. We have calculated, based on observed neutren levels at 902 pcwer, that the P-32 activity, if would be - 1.27 x 10-2{ ; ppb P-31Therefere, C1/=1. existed in we thedo stea=

not generator feedwater, believe activation of P-31 is cccurring in the stea= generators as low levels of P-31 are

=aintained in an AVT che=istry plant.

c. We have scrutinized our laboratory practices regarding the processing of P-32 sa=ples. We have uncovered several deficient areas. First, the procedure required to prepare the sa=ple for counting is highly sensitive to experience and technique. Not all e=ployees perfor=ing the -

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=onthly F-32 procedures were properly cautioned to the sensitivity of the analyses. This is not to say they were not properly qualified. It is si= ply a recognition that sc=e analysts have better technique than ,

others. We have observed, for exa=ple, how easy it is to cross-conta=1nate,

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a sa=ple when handling = ore than one type. We speculate that in July, for

., exa=ple, all three sa=ples, the turbine building p6:p, condensate polisher,

and radwaste, were contaminated when processed concurrently with spiked crcss-check sa ples.

~We have observed that the instru=ent used to count the prepared sa=ples is sensitive to outside sources. We have, for exn=ple, placed pri=ary coolant sa=ples near the instru=ent while it was counting and observed

"" a false indication. It is possible that this could have cecurred on occasion.  ;

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d. We are evaluating the use of the instru=en: we chese for :hese analyses in the range in questien. A Seck=an liquid s:in:111stien detector, Mcdel LS-1CO, is used to count :he prepared sanples. The instrumen:'a calibratien is excellent. We have tested it with prepared knewn sanples, we have traded s'a=ples with two other labs and we have had the f ac:ory represents:1ve check cut the instru=ent. It appears, hcvever, that the instrunent nay not be reliable for coun:ing sa=ples of very icv activity.

Samples that produce counts only slightly abeve backgrcund =us be ccented for extended perieds. **e

= were unaware of this require =ent until ve started cur investigation and talked with the Beck =an appli-caticus experts.

e. Finally, we put tege:her a table (see Table I) c s"--arize the data fer the third and fcurth quarters for 1980, the =ce:h of January 1981, and the =enth of February 1981. As can be seen frem the table, it is pessible to reach different ennelusiens. . Ter exa=ple, the Oece=ber 1980 data shews no activity in the :urbice building su=p, yet January 1981 does. Bcth were =onths of reasenable Ices reac:cr e;eratien periods. Is.e Noveeber 1980 data for the cendensate polisher shews =cre activity than the radvaste system. This hardly seems Icgical. As a =atter of fact, cene of the activity attributed to the seccadary cycle seems icgical and that is the problem. Until we can cperate the unit again and cc11ect new samples, we are net certain that P-32 ever existed in the secendary cycle. -

III. The Offsize Ecse Calculatica Manual (OCCM)

The CDCM appreved for Sequcyah recognizes a li=ited list (five) of isotepes that must be evaluated =cn:hly for dcse centributien. They were chosen to be the major isotopes of cencern and ccusequently all other isote;e activf ries which are repcrted men:Ely by the plant to the Divisica of Occupational Health and Safety are not evaluated for dese censideratica until the end of the quarter.

Thereiere, the total effect of the July 1980 data en the third quarter data was not realized _ until October 1980 when the quarterly analysis was perfor=ed.-

IV. Supportive Data-Tables II and III, ' attached, detail third and fourth quar:er liquid effluent _

calculated deses for all activities caused by Sequoyah Nuclear Plant r eleases.

These tables shev that only the dose to the bene was exceeded and that the

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major pathway was through fish. -Ita tables are fectnoted to shew the centri-

butica due to the seccndary cycle _and radvas:e.

Tables IV and V, attached,' detail third and fourth quar:er liquid effluen:

calculated doses for fish censumptien.alene for all analy:ed isotopes. It-should _be ncted that the culy'isotcpe of significance is P-31. The tables

- are footnoted to shcw the centributica due to the seccedary cycle and radvaste.

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IV. Supportive Data (continued)

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

Appendix 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 follewup report will be prepared and sent to the Commission 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 will 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.

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Communications 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 F-32 in the secondary cycle of Sequoyah Nuclear Plant for the last half of 1980. It does, however, point out that there is eAcugh 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 esiculations 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 been confirmed to exist by independent analyses and are present in the plant rodwaste 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 P1JLNT ,

SPECIAL REPORT 80-8 SIMPLIFIED SKETCil 0F LIQUID EFFLUENT RELEASE POINTS ,

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Steam Cenerator Blowdown to Environment (may be recycled to llotwell if desired)

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pical TY Pical WR Secondary Loop __Cou211ng Thru Cycle with Condensate Polisher Regeneration Steam Generators Full Flow N '

Environment (ma) Le

' ' direct or to Turbine Building Sump) f*"Pf[rs s

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To waste water ' #

@ypical Waste Secondary System Leakage to Environcent processing (may Trocessors (typically processed thru Turbine be bypassed if Building Sump) of required quality)

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Release to Environment

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. SEQUQJAH NUCLEAR FIANT1

. SPECIAL REPORT 80-8

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'Blvdwn Act pc/mi 0 0 0 0 0 0 6.3 x 10-7 0

- Mrs. Rx critical 371 151 19.6 143.5 330 572 496 94.2

. % Max PWR 0. 0 0 30 75 90 100 98 Max - PS: Con 0 0 0 274 860 1027 1156 1088

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• APPENDIX A RADIOLOGICAL IMPACTS ON FINISHED DRINKING *.'ATER SUPPLIES Postulated radiological inpacts 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 conpliance with the requirements of 40 CFR 141. The average concentrations of beta-particle and photon radioactivity from mansade radionuclides in drin' ing water were well below an annual dose equivalent to the total body or any internal organ of 4 millirem / year. The attached table lists the annual dose contributed by each isotope' released.

.

f

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• O d o

.

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.

'

• APPENDIX A WATER INCESTION DOSES (MREM) FOR 1980 FIRST PUBLIC VATER SU? PLY DOWNSTREAM

• FROM SEOUOYAH NUCLEAR PLL'Tr Bone P_e,rcent Total Body Percent H-3 2.27E-6 2.44E-6 0.3 Na-24 2.20E-6 2.20E-6 0.3 P 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 1.15 E-5 0.2 1.14E-5 1.3 Co-60 2.25E-6 2.24E-6 0.3 Kr-85 0.0 0.0 Sr-89 3.89E-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-11 Zr-95 -3.34E-10 7.2SE-11 Nb-95 6.88E-11 2.06E-11 Tc-993 2.43E-11 '

8.76E-10 1-131 1.63E-6 1.34E 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-8 2.19E-8 Ce-144 2.00E-8 1.08E-9 Pr ,144 1.14E-12 5.81E-14 W-187 2.77E-9 8.11E Total 6.07E-3 99.8. 8.67E-4 100.2

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

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.

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.

APPENDIX 3 4

RADIOLOGICAL ANALYSES OF C;7tR0!.SEN AL MIDIA 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 results of analyses of sa_ples of drinking water indicate that there are no signifi-cant differences between concentrations in the upstreas sources when

• conpared to the downstress sources. Further, there are no significant differences between preoperational resulta.and results fres'the July to December 1980 time period.

Tablas are attached which provide available results of analyses of sanples of surface water, fish, and sedi=ent for 1980 in the Sequoyah e

environs. There appear to be no radionuclide concentrations indicative

.of significant influence fres Sequoyah Nuclear ?lant operations.

i

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APPENDIX B .

.

GROSS BETA CONCENTRATIONS IN DRINKING WATER SEQUOYAH NUCLEAR Pl. ANT l: -

Jul.Y-DECDilsER 1980 Activity, pC1/1 Upstream Downstream Collection Date Dayton Daisy Cleveland C. F. Industries Chattauooga E. I. DuPont 7-7 1.2" 1.5" 0.8* 3.0 2.1" 0.9"#

0-4 2.6 '1.5" 1.0" 2.5 1.3" 1.4

- I 1.7' O.6" 0.3"a 3.5 1.5" 1.8" 9-29

'

'2.1" 2.4 1.l 4.0 1.7" 1.9" 10-27 2.3" 1.5" 1.9* 2.7 1.5" 1.7" 11 3.6 .1.3" 1.3" 2.5 2.6 2.6 8

12-22 6.1 1.4" 1.0" -

3.0 2.3" 1.2 Averapi, all data July-Dec. 1980 2.8t1.6 1.510.5 1.110.5 3.010.6 1.910.5 1.610.6 1979 2.811.4 1.410.7 1.310.7 3.611.9 2.310.4 1.910.7 1978 3.111.1 2.210.4 2.911.7 4.412.2 2.510.8 3.310.3 l

! for three stations ,

l, for July-Dec. 1980: 1.811.2 2.210.8 l Average, Values >Lt.D only

July-Dec. 1980 4.111.8 2.4 < LLD 3.010.6 2.6 2.6 1979 3.611.2

'

2.4 2.4 4.011.8 2.710.2 2.710.4 1978 '3.611.0 2.610.1 3.511.4 4.812.1 3.210.5 3.310.3 i

l for three stations I for July-Dec. 1980: 3.711.7 2.910.5

a. Vaine reported is less than the nominal lower limit of detection (LLD) of 2.4 pC1/1.

L b. Uncertainty reported is one standard deviation.

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APPENDIX B

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CROSS A1. Pila AND BETA CONCENTRATIONS IN SURFACE WATER .

S_Ef}t10YAll NUCI. EAR ' Pl. ANT Jill.Y-DECENHER 1980 Activity, pCf/1 Upstream Downstream Tlut 473.2

,

Tiut 497.0 TRM 483.4 Collection Date u Il a _

6 a __ 8

,

0,7 es,b- C -0.6 "'I' 1.9

-0.5 a,b- t,9c 2.0 7/7-

-0.5 a,b 2.1 C .

1.5" d

-0.5 a,b 1.5 C -0.6 a,b 1.5 C -0.8 "'"

j3g

"'I e -0.2 a,b 1,9 c a 1.C -0.1 1.' 9 f2 g .

3.1 0! 3 ,' . 1.7 " ' 3.8 4.0 9j

.1 1.3 a 3.6 3.0 1 UC 34 4.2 23 g g3 2.1 93 3' a 3.6 10/2*3 i1/25 ~3.6' 6.8 0.9 a 2.3 c 0.0 8 3.0 1.1 a 2.7 3.4 5.4 0.0 12/19-Average, all data e 2.611.5 1.111.8 3.0t1.5 0.711.8 2.610.8 July-Dec. 1980 2.0 t 2.7 2.411.0

' 0. 9 t 1.1 - 3.6t3.0 0.710.6 4.613.0 0.413.0 1979 4.814.1 0.410.7 3.411.5 0.710.6 3.711.3 0.810.9

.1978 Average: Values >l.l.D only -

4.71 3.2 3.911.7 3.410.0 4.510.8 3.211.2 3.210.3 July-Dec. 1980 3.110.9 1979 3.6 5.413.4 < t.t.D 5.413.0 < t.I.D 3.811.5 < l.l.D 3.911.3 3.0 6.914.0 1978 <l.1.0

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

b. Hegative value is.an artifact of counting statistics and does not.'lafer a nee.ative activity.

c. Value reported ta less than the nominal 1.1.D.of 2.4 pCi/1.

d. Ruplicate sample,

e. Uncertainty reported la one standard deviation.

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APPENDIX B

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CONCENTRATIONS _OF RADI0 ACTIVITY IN FISil .

SEQUOYAll NUCLEAR PLANT

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APRIL-MAY 1980

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Sampling Activity, pCi/a, dry weight I.ocation Gross Cross 137 Cs "8 K 88 Sr (Reservoir). n 0 a s S r.

Species 0.1 0.1 0.5 0.1 0.02 -

- LI.D -

White crappie Watts Har*' O.9 27.2 0.8 0.I' O.15 14.5 Chickamauga 0.5 25.4 0.2 9.1 0.09 17.1 (Flesh) b 0.14 15.5 Nickajack 1.6 15.1 -1.0 0.3 1.0 '20.2 -0.4 0.2 0.12 16.3 Average 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) O.9 27.6 1.6 0.0 0.03 12.4 Nickajack '

1.0 22.0 0.8 0.0 0.05 13.0 Average c Smallmouth 0.4 0.07 17.0 Buffalo Watts Bar a 1.9 14.7 0.0 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

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1.0 16.0 -0.6 0.0 0.06 13.4 Average Sraa11mout h 0.2 b 0.2 0.12 7.9 Watts Bar' 1.1 9.2 Buffalo 0.5 14.2 -0.1 0.1 0.04 6.7 (whole) Chickamauga 9.8 Ulckajack 1.3 28.5 0.4 0.0' ND 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.

1.LD-Lower limit of detection.

HD -No activity detected.

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APPENDIX B ,

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CROSS AI.P:(A AND BETA CONCENTRATIONS IN SEDIHENT

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SEQllOYAll NUCl. EAR PLANT JUI.Y-DECEMBER 1980 ,

Date Activity, pC1/g, dry weight ColIected Upstream Downstream TRM 496.5 TRM 483.4 Trit 480.8 TRFI 472.8

.1 n- 6 n 6 n 6

__

~ 6_

.3.8 29.4 2.1 20.3 3.6 21.6 2.4 19.4 8/14 2.8 13.I 1.7 12.5 -

.4 26.6 3.0 20.0 11/18-21 _ _

3.3r0.7" 2L.3111.5 1.910.3 16.415.5 3. 5 z't .1 24.113.5 2.710.4 19.710.4 Average:

Slioreline Stations .

Tiut 485 TRM 478.2 TRH 477 n 6- n 6 ,a 6 8/28 1.3- 9.3 ,

1.' 2 3.0 1.9 6.3

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a. Uncertainty reported is one standard deviation.

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. . APPENDIX B RADIOACTIVITY IN FISH SEQUOYAH NUCLEAR PI. ANT NOVEMBER-DECEMBER 1980 Sampling Location Species (Reservoir) Activity pCi/g, dry weight 137 Cs 40g White Crappie Watts Bar a 0.18 19.0 (Flesh) Chickamauga 0.10 17.4 Nickajack 0.08 16.8 Averageb 0.09 17.1

• Channel Catfish Watts Bar a 0.11 16.4 (Flesh) Chickamauga 0.04 12.1 Nickaj ack 0.02 12.6

- Average b 0.03 12.4 Smallmouth Buffalo Watts Bar* 0.03 11.5 (Flesh) Chickamauga 0.05 11.4 Nickajack 0.03 9.5 Average b 0.04 10.4 Smallmouth Buffalo Watts Bar 2 0.02 7.4 .

(Whole) Chickamauga 0.03 6.3 Nickaj ack 0.01 6.9 AverageD 0.02 6.6 '

c-Upstream impoundment. .

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b-Average of results from downstream impoundments.

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APPENDIX C SPECIAL REPORI 80-8 I.

SUMMARY

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

The report ide'ntifies 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 OPERAELE. The appropriate portions of the system shall be used to reduce the radioactive materials

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in liquid wastes prior 'to their discharge when the projected dos.es due to the liquid effluent from the site when averaged

- over 31 days would exceed 0.06 mrem to the total b,ody or 0.2 mrem 1to any organ.*"

It could be in't erpreted that Sequoyah exceeded these limits for-the last half of 1980. However, the Sequoyah design does not per=it processing lof turbine building' sump discharges and in

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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 investigation was started-that revealed the ~ subject LCO was exceeded -

for the months of. January, 1981 and February, 1981. This infor-mation would technically not have been available until1the end of-the first quarter'of~1981. But sus more information was made available to the plant staff, specifi~cally the high re-concentration factor applied to P-32,l it seemed prudent to do an early evaluation.

The evaluation concluded that the LCO limits ,would be exceeded because-sufficient; volumes ofL

• mary system water were discharged -

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without' processing. 1These disenarges were previously made.using only : the: five isotopes mentioned uin the ODCM as source ' terms ' for calculating release concentrati,ons. Using this' methodology, limits were well below allewable technical specification values' for dose - ~~

. and 10 CFR 20, Appendix 'I release concentrations, (Refer to Sequoyah-MonthlysNRC Reports _for effluent release values)

Prior'toIFebruary,.1981, Sequoyah elected not-to use its design

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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 1 t* .Per reactor unit l

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

Thirdly, Sequoyah has elected to use an outside vendor to process evaporator bottoms and spent resins. Due to problems witn the vendor contracted, previously reported to the Cc= mission, Sequoyah avoided use of the evaporators.

During the f all of 1980 when it became evident that the installed evaporators would not be eccnomical to operate, TVA proceeded to purchase the services of a vendor to demineralize radwaste.

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 after 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 li=it due to P-32 or other isotopes. ODCM changes will be made to evaluate P-32 on a monthly basis and all future radvaste releases will be processed.

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