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October 8, 1982 NRC/TMI-82.062

U J. .} IIH OU I J.UI1

JMIPO HQ r/f TMI SITE r/f

~ENTRAL FILE NRC PDR LOCAL PDR Site Operat ions

File

Ma«>RANDUM FOR: Harold R. Denton. Director

FRC»t:

SUBJECT:

Office of Nuclear Reactor Regulation

Bernard J. Snyder. Program Director THI Program Office

LAke H. Barrett. Deputy Program Director TMI Program Office

NRC TMI PROGr~ OFFICE WEEKLY STATUS REPORT

Enclosed i s the status report for the period of October 3 - October 8. 1982. Major items included 1n this report are:

Liquid 'f fluents

EPA and NRC Environmental Data

Rad ioactive Material and Radwaste Shipments

Submerged Oemineralizer System Status

EPICOR II

Reactor Building Entries

EPICOR II Prefilter Shipment Status

Groundwater Monitoriug Program

THI Aerial Radiological Survey

Public Meetings Originol signod b~ La.ko Ho Barret.'-_,......

lake H. Barrett 8211040071 921008 PDR ADOCK 0~00320 R PDR

Deputy Program Director TMI Program Office

Enclosure: As stated

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Harold R. Denton Bemtrd J. Snyder

cc w/encl: EDO OGC Office Directors Commissioner's Techn1ct1 Assistants HRR Div1s1on Directors NRR AID's Regional Administrators IE 01v1s1on Directors TAS EIS TMI Program Office Staff (lS) PtiS EPA DOE Rl 01v1 s1on D1rectors Public Affai rs . RI State L1a1son, RI

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OFFICIAL RECORD COPY

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Plant Status

NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT

October 3, 1982 - October 8, 1982

Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) to reactor building ambient.

Available Core Cooling Modes: Mini Decay Heat Removal (MOHR) system.

RCS Pressure Control Mode: RCS is vented to the reactor building.

Major Parameters (as of 0500, October 8, 1982) (approximate values) Average Incore Thermocoupl es* : 113°F Maximum Incore Thermocouple*: 130°F

RCS Loop Temperatures: A B

Hot Leg** 94°F 93°F

Cold Leg g~ 77°F 76°F 78°F 78°F

Pressure : The reactor coolant system is vented to t he reactor buildi ng.

Reactor Buil ding: Temperature: 75°F Pressure: -0.20 psig Airborne Radionuclide Concentrati ons:

1.8 E-6 uCi /cc H3 (sampl e taken 10/ 4/ 82)

3.4 E-10 uCi / cc part icu lates (sample taken 10/ 1/ 82 )

Kr85 concentrations are below the lower limi t of detection (LLD): 6.2 E-6 uCi/cc

1. Effluent and Environmental (Rad iolog ical) Informati on

Liqu id eff luents from t he TM l s i te re leased to the Su squeha nna River a ~ t e r ~ roc e s s in9, were ~~ de ~i th i n the regulatcry l i~i ts and i n ccccrda nc~ l·:i th r.=.. c I' Ec,unener.t s c.r.o Ci ty cf lc"'Co~te r ,;~r eeren t .

During t he period October 1, 1982, th rough October 7, 1982, the effluents contained no detectable radioactivity at the discharge point and individual effluent sources, which originated within Unit 2, contained no detectable radioactivity.

*Uncertainties exist as to the exact location and accuracy of these readings. **The primary water level is below the hot leg temperature sensors.

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Environment al Protection Agency (EPA) Environmental Data

•• The EPA Middletown Office has not received the environmental Kr-85 for the samples which were taken subsequent to September 10. 1982. from the EPA's Counting Laboratory at Las Vegas. Nevada. These resul ts will be included in a subsequent report.

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 October 1, 1982 through October 1. 1982.

3. NRC Environmental Data

Results from NRC monitoring of the environment around the TMI site were as follows :

The followi ng are the NRC air sample analytical results for the onsite continuous air sampler:

Sample

HP-339

Period

September 27 - October 6, 1982

1-131 . (uCi/CC)

<6.6 E-14

Cs-137 {uCi/CC)

<6.6 E-14

4. Licensee Radioactive Material and Radwaste Shipments

On October 4, 1982, two Unit 1 solidified evaporator bottoms were shipped to U.S. Ecology (Hanford Burial Site}, Richland, Wa shington.

On October 5, 1982, two Unit 1 liquid samples were mailed to Radiation Management Corporation, Philadelphia, Pennsylvania .

On October 6, 1982, two Unit 1 solidified evaporator bottoms were shipped to U.S. Ecology, Richland, Washington .

On October 6, 1982 , fi ve Unit 1 spent fuel pool samples (fi l ter paper swipes) were shipped to Babcock and Wilcox, Lynchburg Research Cer.ter, Lynchburg, Vir9inia.

On October 7, 1982, one Unit 2 EPICOR II pref i lter (PF-2) was shipped to EG&G Incorporated, Idaho Falls, Idaho.

On October 7, 1982, two Unit 1 solidified evaporator bottoms were shipped to U.S. Ecology, Richland, Washington •

Major Activities

1~

. I

4.

5.

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EPICOR II. The EPICOR II system continued to process SOS effluent during the ·past week. latest parameters for the system are shown in Attachment 1.

Reactor Building Entriesi Reactor building entries were condueted on ~onday, Wednesday, and Friday, October 4, 6, and 8, 1982. Polar cra ne decontamination, including manual scrubbing with a mild detergent, was the predominant activity inside the reactor building. A brief inspection of components and wall surfaces below the 305 ft. elevation was conducted using a closed circuit television camera. A "dirt ring," showing the basement high-water level, was visible on the D-ring wall. The three-entry-per-week schedule is expected to continue during the reactor building decontamination effort.

EPICOR II Prefilter Shipment Status. On October 7, 1982, the third 1n a group of 49 EPICOR 11 pref1lters (PF-2) was shipped from TMI to the Idaho National Engineering Laboratory (INEL) in Scoville, Idaho. The PF-2 liner and shipping cask (CNS-120-3) were inerted with nitrogen as an added safety precaution to ensure that no combustible gases will exist during shipment. The hydrogen-oxygen composition in the liner will be maintained at <2. 5~ hydrogen and <0.5~ oxygen . Two EPICOR II prefil ters (PF-6 and PF-7) have been prepared for sh ipment and ar~ awaiting the availab ility of a type B shipping cask. (Because of a drain plug removal problem, the H~ -200 cask will not be ava il able until the week of October 11. 1982.) Currently, GPU is preparing pref il ter PF-8 for sampl i ng and inerting.

Groundwater Monitorin~ Program. Periodic sampling of TMI groundwater began in January 1980 n an effort to detect any potential leakage from t he contaminated water in the basement of the reactor building . When the submerged demineralizer system began processing reactor building water, the basement contained approximately 600,000 gallons of highly radi oactive water (>150 uCi/ml). There was a concern, if the reactor building leaked, that the leakage could contaminate Three Mile Island groundwater. However , the monitoring program has accumul ated data to indicate that there was no leakage from the reactor building. The program did identify some groundwater contamination which resulted f rom leakage from the borated water storage tank (B~ST).

The possibility of groundwate r conta"ination fro~ the potential sources c1 lea~~SE has beEr 1·e~uced. Except for a p~r1o~ic adoiti on of water fron on -going rcbc:or buildi~g decontamina tion, the water in the reactor building has been removed. A leakage collection trough and more sensitive level indicating equipment have been added to the BWST. The effectiveness of these measures will continue to be evaluated by the groundwater monitoring program.

Attachment II includes a sketch of the groundwater sampling locations. The most recently recorded tritium concentration and the highest recorded tritium concentration are noted at each location. Pre-TMI monitoring data indicate that surface water, drinking water and precipitation in the

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TMl area will contain an average of 300 pCi/L of tritium with values as high as 600 pCi/1 within the expected range. The highest TMI groundwater contamina~ion was recorded in test boring 17 on March 23, 1982 {1.1 x 10 pCi/L). Test boring 17 is in an area considered as restricted and the maximum permissib1e8concentration (MPC) for tritium in restricted areas is 0.1 uC1/ml (1 x 10 pC1/L) . ·

Tritium was the predominant radioisotope detected in the groundwater. However, sporadic trace levels of radioactive cesium have been detected in test boring 2. On June 1, 1982, 11 pCi / L of antimony ·l25 was detected in test boring 17. {This antimony concentration was just above the lower limit of detection.) Subsequent samples from test boring 17 did not contain any detectable antimony.

6. TMI Aerial Radiological Survey. An aerial radiological survey of the Three Mile Isla nd area has been tentatively scheduled to begin Thursday, October 21, 1982. The survey will be performed by EG&G under contract to the Department of Energy and i s expected to require four to five days of low level helicopter overfl ight (~250 ft . altitude) of a five square mile area. This survey is a follow-up to the EG&G aerial radiologi ca l survey of TMI conducted during August 1976.

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Futur@ Meeting

1. On October 12, 1982, Lake H. Barrett will meet with the Concerned Mothers of Middletown to discuss THI-related issues.

2. On November 9, 1982, the NRC commissioners wi11 hold a public meeting to discuss the potential restart of TMI Unit No. 1. The format for the meeting is discussed in the attached press release and order (Attachment III). Further details regarding location and local contact for publ ic statements will be included in press releases when they become available.

Radionuc1ide

Cesium 137

Strontium 90

Radionuclide

Cesium 137

Strontium 90

ATIACHMENT I

SDS PERFORMANCE FOR BATCH NUMBER 36

Average Influent {uc/ml)

2.5 X 101

5.8

Average Effluent {uc/ml)

1.0 X 10-4

7. 9 x 1 o-4

EPICOR II PERFORMANCE Batch 143

Average Influent {uc/ml)

7.4 X 10-S

1. 2 X 10-4

Average Effluent {uc/ml)

3. 75 X 10•7

9. 3 X 10-6

Average OF

2.5 X 105

7.4 X 103

Average OF

1.97 X 102

1.29 X 101

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