ML20033A881

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Forwards TMI Program Ofc Weekly Status Rept for Wk of 811101-07
ML20033A881
Person / Time
Site: Crane 
Issue date: 11/09/1981
From: Barrett L
Office of Nuclear Reactor Regulation
To: Harold Denton, Snyder B
Office of Nuclear Reactor Regulation
References
CON-NRC-TMI-81-062, CON-NRC-TMI-81-62 NUDOCS 8111300075
Download: ML20033A881 (9)


Text

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DISTRIBUTION TMIPO r/f (HQ)

TMI SITE r/f 4 E4TlAL FILE NRC PDR LOCAL PDR Site Operations File Novecher 9.1931 NRC/TMI-81-062 MEMORANDUM FOR:

Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director TMI Program Office FROM:

Lake H. Barrett. Deputy Program Director TMI Program Office

SUBJECT:

NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of November 1-7. 1981.

Major items included in this report are:

Liquid Effluent Releases N2C and EPA Environmental Data Radioactive Material and Radweste Shipments tn 4

Submerged Demineralizer System Status EPICOR II E

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q f;' u.s.wom==1981> 3 NOV16 Reactor Building Entries

'o** 7 Interim Staging Module Status k

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Public Meetings

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fe o?Y Lake H. Barrett l

Deputy Program Director TMI Program Office

Enclosure:

As stated

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OFRCIR REORD COW

Harold R. Denton November 9,1981 Bernard J. Snyder cc w/ enc 1:

EDO OGC Office Directors Commissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors TAS EIS TMI Program Office Staff (15)

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EPA DOE Projects Br. #2 Chief, DRPI, RI DRPI Chief, RI Public Affairs, RI State Liaison, RI TM*b7 TMIP0 TMIPb g[/fMIP0eoppy-

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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of November 1-7, 1981 Plant Status Core Cooling Mode:

Heat transfer from the reactor coolant system (RCS) loops to reactor building ambient.

Available Core Cooling Modes:

Decay beat removal systems.

Long term cooling "B" (once through steam generator-B).

RCS Pressure Control Mode: Standby pressure control (SPC) system.

Backup Pressure Control Modes: Mini decay heat removal (MDHR) system.

Decay heat removal (DHR) system.

Major Parameters (as of 0500, November 6,1981) (approximate values)

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Average Incore Thermocouples : 113 F Maximum Incore Thermocouple:

142*F

...d RCS Loop Temperatures:

1 A

B

't Hot Leg 107*F

~110"F

' Cold Leg (1) 69*F 72 F "5

(2) 69*F 69*F

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RCS Pressure: 96 psig j

Reactor Building: Temperature :

66 F Water level:

Elevation 288.4 ft. (5.9 ft. from floor)

.1 via penetration 401 manometer '

Pressure :

-0.15 psig Concentration : 8.6 x 10-b uCi/cc Kr-85

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(Sample taken 11/4/81)

Effluent and Env_ironmental (Radiological) Information

'1

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Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster. Agreement dated February 27, 1980 i

During the period October 30, 1981, through November 6,1981, the effluents contained no detectable radioactivity at the discharge point and individual effluent sources which originated within Unit 2 contained no detectable radioactivity.

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Environmental Protection Agency (EPA) Environmental Data.

Results from EPA monitoring of the environment around the TM1 site were as follows :

3

- The EPA measured.KR-85 concentrations (pCi/m ) at several environmental monitoring stations and reported the following resul ts.

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Location October 9 - October 23,1981 l (pC1/m3)

Gol dsboro 24 Observation Center 26 Middletown 30 Yorkhaven 30 All of the above levels of Kr-85 are considered to be background level s.

-1 No radiation above normally occurring background levels was J

detected in any of the samples collected from the EPA's air q

l and gamma rate netwcrks during the period from October.28,1981, through November 5,1981.

l 3.

NRC. Environmental Data.

Rssults from NRC monitoring of the environment I

around the TMI site were as follows:

-T The following are the NRC air sample analytical results for

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the onsite continuous air sampler:

I-1 31 Cs-137 Sample Period (uCi/cc) ECi/cc) i

,h HP-292 October 28, 1981 - November 4,1981

< 8.6 E-14 <8.6 E 14 l

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Licensee Radioactive Material and Radwaste Shipments.

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On Wednesday, November 4,1981, an EPICOR II dewatered resin '

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liner (F-8) was shipped to U.S. Ecology, Richland, Washington.

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On Wednesday, November 4, 1981, 20 metal containers (boxes) of.

I Unit 1 LSA noncompacted waste were shipped to U.S. Ecology, Richland, Washington.

l On Thursday, November 5, 1981, 50 drums containing Unit 2 contaminated laundry were shipped to Tri-State Industrial Laundry Inc.,,Utica, New York.

On Thursday, November 5,1981, a one liter, Unit 1 WECST

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(waste evaporator condensate storage tank) composite sample was mailed to Teledyne Isotopes, Westwood, New Jersey.

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De Friday, November 6,1981, one EPICOR II dewatered resin if ner (liner K-2) was shipped to U.S. Ecology, Richland.

Washington.

On Friday, November 6,1981, one EPICOR II dewatered resin lir.er (liner F-9) was shipped to U.S. Ecology, Richland.

Washington..

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i On Friday, November 6, 1981, 35 drums and seven metal boxes containing Unit 2 compacted and noncompacted waste, and one

' f EPICOR II dewatered resin liner (liner 2K-1) were shipped to

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U.S. Ecology, Richland, Washington.

  • i Major Activities.-

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1.

Submerged Demineralizer System (SDS).

Processing of batch number 8-was completed on October 31,.1981. During October 31

- November 1 4-1D 1981, approxitately 40,000 gallons of reactor building sump water i

were transferred to the SDS feed tanks in the fuel handling building.

L This transfer brings the amount of water transferred from the a]

l reactor building -sump to a total of approximately 205,000 gallons.

i Processing of batch number 9 commenced on November-7,1981.NThis batch includes the above 40,000 gallons of water transferred and

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approximately 7,000, gallons of water from a reactor coolant bleed 5

l '3 tank.

As of November 5,1981, approximately 180,000 gallons of.

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reactor building sump water had been processed. -

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.w a.9. cc,am.p.

Following processing of batch 9, the licensee has scheduled a short.Q/

outage period (less than one week) to replace ion exchange vessels;i:

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and perform minor maintenance on system valves to increase flow through the pool water cleanup system.,SDS performance parameters"'

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j $w ~ p *..for batch 8 are attached.

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u Processing of SDS effluent through the EPICOR II system Iy.p,.e,3.n Md i

2.

EPI COR _ I_I.

contirued this week.

As of November 5,'1981, approximately 170,000.?he e M i.jilf gallons of reactor building sump water had been polish'ed. Linerc. ;

l Eu F-8 was shipped on November 4,1981.to a commercial burial. facility +

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near Richland, Washington. for disposal.

Recent perfonnance parameters ;

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for EPICOR II are attached.-

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Reactor Bui_lding Entries.

The third reactor building (RB) entry (entry 19) in support.of the gross decontamination experiment was completed on Thursday, November 5,1981.

During the first three entries, housekeeping and trash removal were the most time consuming 1

tasks in the RB.. Surveys in accessible areas of the RB have not l

detected any radiological changes which could be attributed to the transfer of 205,000 gallons of water from the R8 basement to the l

SDS.

l Three of the four scheduled gross decontamination experiment entries l

have'been completed.

However, the schedule for specific tasks has I

fallen ~behind in several areas.

Delays in work to install the high l

pressture water hose, the power lift, new radio antennas, and electrical,

't The power for support equipment appear to be the most signi'ficant.

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l' impact of the existing delays on the overall decontamication experiment:

schedule has not been assesced. The decontamination experiment was originally sci.eduled to be completed in December 1981.

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h On Friday, November 6,1981, one EPICOR II dewatered resin liner (liner K-2) was shipped to U.S. Ecology, Richland, Washington.

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On Friday, November 6,1981, one EPICOR II dewatered resin lirer (liner F-9) was shipped to U.S. Ecology, Richland, Washington..

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j On Friday, November 6, 1981, 35 drums and seven metai boxes containing Unit 2 compacted and noncompacted waste, and one.

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EPICOR II dewatered resin liner (liner 2K-1) were shipped to U.S. Ecology, Richland, Washington.

l Major Activities.

1.

Submerged Demineralizer System (SDS).

Processing of batch number 8 was completed on October 31,.1981. During October 31

- November 1 "I

1981, approximately 40,000 gallons of reactor building sump water were transferred to the SDS feed tanks in the fuel handling building.

-i This transfer brings the amount of water transferred from the reactor building sump to a total of approximately 205,000 gallons.

Processing of batch number 9 commenced on November 2,1981.%.This batch includes the above 40,000 gallons of water transferred and 5

approximately 7,000, gallons of water from a reactor coolant bleed i'

tank.

As of November 5,1981, approximately 180,000 gallons of reactor butiding sump water had been processed.

, y1 Following processing of batch 9, the licensee has scheduled a short outage period (less than one week) to replace ion exchange vessels.

~

j' and perform minor maintenance on system valves to increase flow

~ -i through the pool water cleanup system.

SDS perfc rmance parameters for batch 8 are attached.

. i. _

2."

EPICOR II.

Processing of SDS effluent through the EPICOR II system ?

contirued this week.

As of November 5 1981, approximately 170,000.

I, gallons of reactor building sump water had been polished.. Linerc.._ _ -

.?

F-8 was shipped on November 4,1981.to a commercial burial facility near Richland, Washington for disposal.

Recent performance parameters for EPICOR II are attached.-

3.

Reactor Bui_1 ding Entries.

The third reactor building (RB) entry (entry 19) in support-of the gross decontamination experiment was completed on Thursday, November 5,1981.

During the first three entries, housekeeping and trash removal were the most time consuming tasks in the RB.,. Surveys in accessible areas of the RB have not detected any radiological changes which could be attributed to the transfer of 205,000 gallons of water from the RB basement to the SDS.

Three of the four scheduled gross decontamination experiment entries have been completed.

However, the schedule for specific tasks has fallen behind in several areas.

Delays in work to install the high pressure water hose, the power lift, new radio antennas, and electrical power for sup' port equipment appear to be the most signi~ficant.

The impact of the existing delays on the overall decontamication experiment schedule has not been assesced. The decontamination experiment was originally scheduled to be completed in December 1981.

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_Two interim staging modules werei r to shipment Q

4 Each module contains 60 storage cells.on site to s Module Status.

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Interim Sta in which were generated by the f% %;$

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IIonstructe the auxiliary building.

i modules contained all the spent res ns off site.

EPICOR 11 system which processed water fromd for disposal at c Ng

? Z:F Forty-nine All the above EPICOR liners which qualifie shipped off site.

l burial criteria and are b w radioactive burial facilities have been EPICOR II prefilters do not meet commercia d les. 'The Department ofto government c M

still stored in the interim staging mo uEnergy has agreed ply tion of the transfer gy facilities for R&D purposes.

will be shipped in earJy 1982 when construc

~O..g j9-k jf-Stl equipment is complete.

used for temporary Periodically, the interim staging modules arelishing resins which are 1 l5

' k ON staging of Unit I waste and EPICOR II poThe Unit' Elia~ste and the EPICOR i

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d are routinely

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used to process SDS affluent.

polishing resins meet commercial burial criteria anThe interim staging

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DEB Al though~

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liners.

periodically to detect leakage from the storeditium have been'a' detected

- U shipped off site.

b trace quantities of radioactive cesium and tr t shown ny in the sump, the quantities of radioisotopes have noLeakage from spent

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N tendency.to increase.. expected to increase sump radioactivity signif can w

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  • Meetings Held

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A meeting was. held on November 3,1981, by B. Snyder with Maryland State f

Delegate Catherine Riley to brief her on TMI-2 cleanup progress and future plans.

Delegate Riley represents the ~ area of Maryland which includes the Susquehanna River and the head of the Cheasapeake Bay. She

.[

has had a continuing interest in TMI-2, including active participation /

h in NRC public meetings held ~in Maryland on the Programmatic Environmental Impact Statement.

In addition to a discussion of the current status of' TMI-2 cleanup activities, Delegate Riley was briefed on future NRC f

studies for further investigation of alternatives for disposition of processed accident water and assessments of potential socio-economic h*

impacts associated with each alternative.

Planned State of. Maryland studies of socio-economic impacts of processed accident water disposition 3

were also discussed.

. }-

Future Meetings

'7 1.

On Friday, November 13, 1981, Lake Barrett will be meeting with D

local mothers to discuss the decontamination experiments and other h2 related TMI-2 issues.

I 14,1981, at 8:00 p.m., Lake Barrett hill 5j 2.

On Saturday, November participate in a panel discussion at the Elizabethtown Public egg Library on the government's response to the TMI accident.

2?q e

3.

The NRC's Advisory Panel for the Decontamination of Three Mile if Island Unit 2 will meet November 16,1981, from 7:00 p.m. to 10:00 p.m.

O in the Municipal Building, 400 South 8th Street, Lebanon.

At the

-d meeting, the panel plans to discuss cleanup financial problems ~

j and the current status of cleanup activities at Three Mile Island.

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d The meeting is open to.the public.
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e ATTACHMENT g

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I SDS Performance for Batch Number. _8 - October 23, _1981 to October 31, 1 981 "x,

Average Average Average Radionuclide Influent Ef_ fluent -

DF (uc/ml)

(uc/ml)

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' Cesium 137 1 x 102 5.9 x 10-4 1.7 x 105 Strontium 90 4.2 8.7 x 10-3 4.8 x 102

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.s EPICOR I_I Performance for Reactor Building Sump Water

.A October 21, 1981 to November 4,1981

.?

.-J Average

. Average Average O

Radionuclide Influent Effluent DF

,J luc /ml)

(uc/ml) g

..)

Cesium 137 7.4 x 10-4 4.5 x 10-7 1.6 x 103 Strontium 90_

8.9 x 10-3 8.3 x 10-6 1.1 x 103 f

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