ML20030B722

Forwards TMI Program Ofc Weekly Status Rept for Wk of 810802-08

ML20030B722
Person / Time
Site:	Crane
Issue date:	08/10/1981
From:	Barrett L Office of Nuclear Reactor Regulation
To:	Harold Denton, Snyder B Office of Nuclear Reactor Regulation
References
CON-NRC-TMI-81-045, CON-NRC-TMI-81-45 NUDOCS 8108240042
Download: ML20030B722 (13)

Text

{{#Wiki_filter:% Y + DISTRIBUTION ~TMI Program Office /HQ r/f i TM) SITE r/f l August 10,1981. 4ENTRAL FILE NRC/TMI-81-045 NRC PDR r LOCAL PDR Site Operations file i' i MEMORANDUM FOR: Harold R. -Denton, Director Office of, Nuclear Reactor Regulation Bernard J.2 Snyder, Program Director TMI Program Office FROM: Lake H. Barrett, Deputy Program Director TMI Program Office

SUBJECT:

NRC THI PROGRAM OFFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of August 2 - 8, 1981. ORIGINAL SIGNED BY: Lake H. Barrett Deputy Program Director TMI Program Office Enclosure : As stated cc w/ encl: EDO OGC Office Directors Commissioner's Technical Assistants NRR Division Directors D NRR A/D's E NL ijgf(Tf/f3 Regional Directors f IE Division Directors TAS 2 I\\UG 171981m Te EIS 1 ~.. C, E g y rans TMI Program Office Staff (15), 4-q l PHS a .s EPA s DOE 't' hk Projects Br. #2 Chief, DRPI, l{I DRPI Chief, RI Public Affairs, RI T. Elsasser 8108240042 810810 PDR ADOCK 05000320 R PDR ! omuk.TMI:P TMI P0 ..T..M..I. : 0,..... ...TM. I TAI ..T.. p.... x 3 P*^"'> .......n,d,mp,,,,,R,,,,,, 3...,e,1,g, ,,,M.....M.b[.T.....S,,,,,,ng. 3.. .. M,q). R y..... .. J. r ra t...... l "*> 8/5.l81 .... //.'.?81 .8/&/81......,.8/g/81,.... 8/. gisi....... 8m.81....... 8 RC FORM 318 ilO'80l NRCM O240 OFFICIAL RECOFiD COPY

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hRC TM1 PROGRT 4 0FFICE WEEKLY STATUS REPORT Week of August 2 - 8, 1981 Plant Status, Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) ~ loops to Reactor Building ambient. Available Core Cooling Modes: Decay heat removal systems. Long term cooling "B" (once through steam generator-B) RCS Pressure Control Mede: Standby Pressure Control (SPC) System. Backup Pressure Control Modes: Mini Decay Heat Removal (MDHR) System. I Decay Heat Removal (DHR) System. l Major Parameters (as of 0500, August 7,1981) (approximate values) Average Incore Thennocouples: 119 F Maximum Incore Thermocouple: 142 F RCS Loop Temperatures: A B Hot Leg 118 F 121. F Cold Leg (1) 73"F 75*F (2) 75 F 75 F RCS Pressure: 93 psig Reactor Building: Temperature: 74 F Water level: Elevation 290.9 ft. (8.4 ft. from floor) l via penetration 401 manometer l Pressure: -0.2 psig I Concentration: 2.3 x 10-6 uCi/ml Kr-85 (Sample taken 7/30/81) Effluent and Environmental (Radiological) Information 1 Liquid effluents from the TMI site released to the Susquehanna River 0 after processing, were made within the regulatory limit,s and in accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980. During the period July 31, 1 981, through August 6,1981, the effluents -3 contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained l minute amounts of radioactivity. Calculations indicate that less than 1 millionth (0.000001) of a curie of Cs-137 was discharged. This j represents less than 0.00001% of the pennissable total liquid activity i as specified in Techniral Specifications for operational commercial reactors. I g, ype g &6 De

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2 Airborne effluents from the TMI site released to the environment, after processing, were made within the regulatory linits and in accordance with NRC requirements. t During the reporting period June 1-30, 1981, the licensee reported the following gaseous releases: Curi es Noble Gases 58.7 Particulates 0.00000237 Tritium 3.8 The above releases represent a small fraction of th9 allowable regulatory limits. The noble gas (Kr-85) release for the month of June, although well within limits and insignificant for environ-mental considerations, was higher than anticipated. A portion of the release can be attributed to Reactor Building purges, and the licensee is currently examining the potential origin of the remainder. Preliminary indications are that the increase may be the result of summer time temperatures affecting the lower sensitivity levels of the effluent monitors. Airborne effluent information will continue to be provided on a monthly basis. 3. Environmental Protection Agency (EPA) Environmental _ Data. The EPA announced on July 6,1981 that, due to a new shipping procedure for Kr-85 samples to the laboratory, the results for the Kr-85 environ-mental monitoring stations around TMI will not always be available on a weekly basis. The NRC will report these results as they become available. No radiation above normally occurring background levels was detected in any of the samples collected from the EPA's air and gamma rate networks during the period from July 30, 1981, through August 6,1981. 4. NRC Environmental Data. Results from N'RC monitoring of the environ-ment around the TMI site were as follows: The fellowing a're the NRC air sample analytical results for the onsite continuous air sampler: ? I-1 31 Cs-137 ^ Sample Period (uCi/cc) (uCi/cc) HP-279 July 30,,1981 - August 5, 1981 <10.0 E-14 <10.0 E-14 I i

5 Licensee Radioactive Material and Radwaste Shipments. l On Monday, August 3,1981, a 40 ml Unit 2 reactor coolaia. sample r was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia. On Tuesday, August 4,1981, one 6' x 6' EPICOR-I dewatered ~ resin liner (liner P-16) from Unit I was shipped to Chem-Nuclear Systems Incorporated, Barnwell, South Carolina. On Friday, August 7,1981, two Hittman steel liners containing Unit 1 solidified evaporator bottoms were shipped to U.S. Ecology, Richland, Washington. Major Activities 1. Submerged Demineralizer System (SDS). Processing of the third batch (approximately,50,000 gallons) of Reactor Coolant Bleed Tank (RCBT) water continued. As of 7:00 a.m., August 7,1981, approximately ' 34,000 gallons had been processed. Preliminary results indicated that the loading on the first zeolite ion-exchange vessel as of August 7,1981 is 740 curies of Cs-137 and 360 curies of Sr-90. This loading represents greater than 99% removal of these radio-. active materials from the process stream. The licensee completed processing the third batch on August 9,1981. Prior to staging and processing reactor building sump water the licensee plans an outage period to incorporate minor system modifications. Staging and processing of reactor building sump water is expected to start the first part of September 1981. 2 TMI Occupational Exposures. shows the data for l' !ts 1 and 2 for 1979 - 1981. The higher exposures for both units in.979 relative to 1980 reflect both reactors being operational early in 1979, the higher level of worker activity immediately after the March 28, 1979 accident, and the effects of radioactive decay and subsequent dose reduction. l provides a comparison of PWR average exposures for the years 1979 and 1980. The two basic conclusions are (1) TMI occupation doses during 1979 (accident year) are comparable to those of other PWR sites, and (2) the difference in occupatinn.al exposure between THI-2 and TMI-l is not significant. Attachments 3A, 3B, and 3C present a breakdown of occupational exposure for the TMI station. These data indicate the number of personnel monitored i for each indicated time period, and number of personnel in each exposure range. As an example, attachment 3A indicates that in 1979, 10,824 people were monitored at the. TMI station, with no measured exposure for 6,869, and 249 received between 0.5 to 0.75 Rem exposure (for instance). The total occupational exposure for the station was 1508 Rem in 1979. The 1979 exposure data directly related to the accident were evaluated in great depth by the USNRC Special Inquiry Group, with the evaluation published in "Three Mile Island, A Report to the Commissioners and to the Public", by M., Rogovin, Director (Attachments 4A, 4B, and 4C). = 4

i Meeting Attended On Thursday, August 6,1981, Lake Barrett met with a delegation of area mothers to discuss various issues related to TMI. Topics discussed ~ included the safety of transportation of radioactive materials, NRC's investigation of Unit 1 operator licensee examination cheating, and Unit 2 funding. Future Meeting On Tuesday, September 1,1981, the Citizens Advisor) P.01 for the Decontamination of TMI Unit 2, will meet from 7:00 p.m. to 10:00 p.m. at the Holiday Inn, 23 South Second Street in Harrisburg, to discuss current activities at TMI. This meeting will be open for public observation. O e e S em e S l 5 O I i t r y

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,y - ~ 1979 SU!'.'*.ARY I;LPORT TM1 STATI0ii-UtilTS I & II i CURREtiT OCCUPATI0 lAL EXTERilAL RADIATIOli EXPOSURE Report period 1/01/79 '- 12/31/79 Personnel monitored 10,824 fio measurable exposure 6,869 Rem s 3 s Ex posure less than 0.1 2,053 0.1 to 0.25 715 0.25 to' O.5 521 0.5 to 0.75 249 0.75 to 1.0 153 1.0 to 2.0 222 2.0 to 3.0 31 l-3.0 to 4.0 6 4.0 to 5.0 5 Greater than 5.0 0 .3 J. l l Yearly total for \\ Units I & II 1508 REM e / / j ATTACHMENT 3A L

SUFF.ARY ROGRT 1 TMI STATIO?l-UlilTS I & II f ,CJRRENT OCCUPAT10ftAL EXTERflAL RADIATI0tl E2POSURE . Repor-t period 01/01/80-12/31/80 Personnel conitored 10,761 No ceasurable 8.433 exposure Rem si,356 Exposure less than 04 s. 539 ".0.1 to 0.25 0.25 to 0.5 304 0.5 to 0.75 62 0.75 to T.0 35 T.0 to 2.0 51 ' 2.0 to 3.0 1 3.0 to 4.0 Greater than 3.0 0' Yearly total for Units 1 & 2 360 ,*1 s. ..y / ATTACHMENT 3B ( - ----

SU:"*.49Y REPORT TMI ST A110 ?-U il15 I & II CURRDiT OCCUPAT10: AL Ex1LRr:AL P.4DIA110;i EXPOSURE f 01/01/81-04/30/81 Report p'eriod 3920 Personnel monitored lio measurable 2717 exposure Rem 974 Exposure less than 0.1 s s 163 _; 0.1 to 0.25 38 0.25 to 0.5 22 0.,5 to 0.75 4 6 0.75 to 1.0 Greater than 1.0 0 e* I-2 Plant total this period 92 c/ m ATTACHMENT 3C

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1*\\- i ret have any discerr.L!c eMact. The Ad Hoc Group simetry Task Group of the President's Commiss on 0" ' reached similar conclusions.170 concluded, after its review of the procedures and ( M* data regarding the occupa'ionaf exposures resulting from the accident, that 'the avai!ab!c data on occu-g. pational exposure at Three M:!e Isfand must be r r*- C. Occupational Exposure EE treated with caution. It may be incomplete."17' We D "- Met 'Ed reported three accident-refated whole-agree with this conclusion. .~ $~ body exposures in excess of the NRC quarterly Emit We find that the accident at TMI-2 resulted in P of 3 rem. These doses were 3.9,4.1, and 4.2 rem. several cxposures in excess of regu!atory IImits to h.J-in add' tion, two workers received overexposures to plant personnel in the first few days following the D. their hands. These doses have been calculated by accident. We find further that the co!!ective occu-M' the NRC at about 50 rem to skin of the forearm of pational dose and the extent of overexposure is not one worker and about 150 rem to the fingers of the targe in relation to the radiat~on fields and contami-other'M. The worker who received 150 rem to his nation levels encountered during the accident, fingers is the same individual who received a although the actual cotective occupational dose is whofe-body exposure of 4.2 rem. (On August 27, not precise!y known. h;, 1979, six workers received overexposures to the g. skin and extremities. The doses, as measured by T1.Ds, were up to 50 rads to the skin and between

f. Health Effects of 1.ow LevelIonizing.,

~ D 40 and 150 rads to the extremities.)172 Radiation h The potential for severe, additional overexpo- _ sures existed during the first few days of the ac-The human health effects of.ioniz2ng radiat. ion -- N@-'cident. Extremely high radiation fields, in excess of m y be classM as- 0) awte somate eMats, (2) b 1000 R/h, existed in the auxifiary building.173 More-developmental or teratogen,ic effects, (3) late somat-5.If over, unauthorized entries to the building were made c eUmts, and (4 guetc eH&ts. - k in violation of station health physics procedures. Amte somat.e eMects,amoh variws forms oka-D Although a person could have been severely diation s,ickness occurring shortly (a few days or C overexposed, there is no evidence that anyone was. w eks) after whofe-body doses of about 100 rad or f[- through June 30 was about 1000 person-rem.m developmental abnormalities fotlow,ing irradiation m The total estimated occupational co!!ective. dose mue. Tuatogmc eHwts,imofve varbus kinds of Table B-25 shows the number of individuals moni-utero. Such effects have been observed in animals Q tored and the co!!ective occupationai doses re-i !! wing doses as low as 5 rad and in humans .I ceived for the period March through September following doses exceeding 50 rad. There is no

3979, evidence associating much srn doses of radia-Table U-2G shows the number of individuals who tion to developmental effects.

received whofe-body doses in excess of 100 mrem De radat,im exposwes caused by the acc,ident during the period from Marco through September msuHed,n,inhal dose cons,idwaW smay,_ N 1979. The data in this table were extracted from an those ass &d wh awte and teratogenc. Met E6s TLD personnel dosimetry report. eMets. De most 5 tant eh of radiaUon on The co!!ecthe dose received by the 1596 Indivi-ch may be mused Mow level radaUon am man w duals receiving doses in excess of 100 mrem is ap-sg which may apr r.r. or cont,inue to appear, at PTximately 800 person-rern. These data show that i ng misvals of t,inx y aposure in the individual g, no individual has received a dose in excess of the irradiated (late somat u effects) or,in his or her pro-aIIowable annual Emit of 5000 mrem.172 The aver-gmy (gmetc eMwtsh @s med in th repst, h - cge dose received by these 1596 individuals was-Iwe r se ers to dosu Mow Mual 10% of that Emit. cwpanma! dose standards of 5000 mrem per Table D-27 contains the dose accumulation rate yeart for the seven individuals receiving more than 3000 mrem during that 7-month period. The table shows that roost of the relatively high individual exposure Lafe Somafic E//ects-The most important late occurred during the first month after the accident. somatic effect of low doses of radiation is the in-The conective occupational dose is sma!!er than crease of incidence of cancer. Most human studies that received by the surrounding population, on populations exposed to radiation (e.g., atomic a!though 'it wi!! continue to rise during recovery ~ bomb survivors in Hiroshima and Nagasaki, radium. operations. Moreover, the Health Physics and Do-dial painters) indicate that radiation-induced Efe ATTACHMENT 4B 401 F~ -

T/.DLE li-25. Occupational dose f.*asch 1 to September 30,19 7 9 'FS Cottective Dose ' FAonth Number of Dosimeters Distributed (person-rem) f f.tarch 1131 334 April ' 4504 140 1Aay 5282 350 June 2973 159 July 2500 (approx.) 63 August 2500 (approx.) 63 September 2472 36 TABLE 1126. Occupational doses in excess of 100 mrem March 1,1979 to September 3C 1979:. Dose Range 100-251-501-751-1001-2001-3001-4001-More than m (mrem) 250 500 750 1000 2000 3000 4000 o000 5000 Number of 648 465 213 118 129 16 4 3 0 Individuals TABLE 1127. Dose accumulation rate for individuals receiving more than 3000 mrem from Y,rch 1, 1979 to September 30,1979"5 L'ose (mrem) .indiv. Indiv. Indiv. Indiv. Indiv. Indiv. Indiv. Period A B C D E F G. j 03/01-03/31 4100 4120 1785 3575 2230 h 85 2360 I 04/01-04/30 160 10 915 40 990 915 1335 j 05/01-06/30 15 30 45 220 100 45 180 07/01-09/30 30 15 395 70 45 335 210 ia l e I shortening is largely due to increased cancer mor-dies also necessarDy invofved exposure to relatively ta!ity.180.1as large doses. Cancers induced by radiation are *m-Radiation-induced cancer is detectable only in a distinguishable fron: those occurring from other statistical sense. A particular case cannot be attri-causes. Radiogenic cancer thus can only be b-buted to radiation 182 Human evidence for ra-ferred on the basis of an excess above the expect-i diogenic cancer comes from epidemiological studies ed naturalincidence. I l conducted on refatively large popufation groups ex-Theoretical considerations suggest that at any posed to deses much larger than those experienced level of radiation no matter how sma!!, some card-J by, the population in the vicinity of the Three M;!e is-nogenic potential exists. Thus far, nearty a!! human j land Statiort Numerous animal studies confirm the data rely on' observations at high dose levels and carcinogenic properties of radiation, but those stu-high dose rates (doses generally greater than 50 / ATTACHMENT 4C 402 q's 7 .}}