ML20032B680
| ML20032B680 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/26/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-060, CON-NRC-TMI-81-60 NUDOCS 8111060065 | |
| Download: ML20032B680 (10) | |
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TMIPO HQ r/f TMI SITE r/f MNTRAL FILE NRC POR LOCAL PDR E "
October 26. 1981 NRC/THI-81-060 e
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9 19 HDIORNiDUM FOR:
Harold R. Denton, Director
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Office of fluclear Raactor Regulation Till Program Office 7' /
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Bernard J. Snyder, Program Director FROM:
Lake H. Barrett, Deputy Program Director TitI Program Offico SU3 JECT:
liRC TMI PROGRNi 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of October 18-24, 1981 Major items included in this report are:
Liquid Effluent Releases fiRC and EPA Environmental Data Radioactive Material and Radwaste Shipments T?tI Occupational Exposures Submerged Demineralizer System Status EPICOR II Reactor Building Integetty Assessment Program Reactor Tailding Entries / Decontamination Experiment Public fleetings Original signod by Lako H. Barrett /
Lake H. Barrett Deputy Program Director Till Progran Offico
Enclosure:
As stated 8111060065 811026" suusaue)
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OFFICIAL RECORD COPY
.L Harold R. Denton October 26, 1981 Bernard J. Snyder.
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EDO OGC Office _ Directors Ccamissioner's Technical Assistants NAR Division Directors NRR A/D's Regional Directors IE Division Directors TAS EIS TMI Program Office Staff (15)
PHS EPA DOE Projects Br. #2 Chief, DRPI, RI DRPI Chi 3f, RI Public AfJairs, RI State Liaison, RI i
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of October 18-24, 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 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, October 23,1981) (approximate values)
Average Incore Thermocouples : 113 F Maximum Incore Thermocouple:
143 F f
RCS Loop Temperatures :
A B
Hot Leg 107 F 110 F Cold Leg (1) 68 F 71 F (2) 68 F 68 F RCS Pressure:
99 psig Reactor Building:
Temperature:
68 F Water level:
Elevation 289.1 ft. (6.5 ft. from floor) via penetration 401 manometer Pressure:
-0.39 psig Concentration : 4.48 x 10-5 uCi/cc Kr-85 (Sample taken 10/19/81)
Effluent and Environmental (Radiological) Information d
1.
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.
During the period October 16, 1981 through October 22,1981, the effluents contained nv detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained minute amounts of radioactivity.
Calcul ations indicate that less than one ten thousandth (0.0001) of a curie of tritium was discharged.
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Environmental Protection Agency (EPA) Environmental Data _.
Results 4
from EPA monitoring of the environment around the TMI site were as f
follows :
The EPA measured KR-85 concentrations (pCi/m ) at several 3
environmental monitoring stations and reported the following results :
. P Location September 25 - October 9,1981 (PCi/m3) 29 Goldsboro Observation Center 23 28 Middletown 22 Yorkhaven l
All of the above levels of Kr-85 are considered to be background levels.
No radiatio'n 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 14, 1981, through October 22, 1981.
3.
NRC Environmental Data.
Results from NRC monitoring of the environment around the IP.1 site were as follows:
I The following are the NRC air sample analytical results for i
the onsite continuous air sampler:
I-1 31 Cs-137 Sample -
Period (uCi /cc_)_ (uCi/cc) i H P-290 October 14, 1981 - October 21, 1981
<7.8 E-14 <7.8 E-14 4.
Licensee Radioactive Material and Radwaste Shipments.
On Monday, October 19,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
On Tuesday, October 20, 1981, two Hittman liners containing solidi fied evaporator bottoms (numbers 17 and 23) from Unit 1 were shipped to U.S. Ecology, Richland, Washington.
On Thursday, October 22, 1981, one EPICOR II dewatered resin liner (liner K-1) was shipped to U.S. Ecology, Richland, Washington.
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5 TMI Occupational Exposur_e_.
Licensee TLD (Thermoluminescent Dosimeter )
h records indicate the following Unit 2 total occupational radiation exposure for 1981 :
k August 1981 :
8 man-rem p
F September 1981:
8 man-rem M
Total 1981 (Jan. to Sept.)
99 man-rem Major Activities
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i 1.
Submerged Demineralizer System (SDS).
Processing of batch number 7 I
T50,000 gallons) was completed on October 18, 1981 and on the same day transfer of another 50,000 gallons of water (batch number 8) from the reactor building sump was commenced.
The transfer was completed on October 20, 1981, and brings the total amount of water transferred from the reactor building sump to approximately 165,000 j
-L gallons. The total amount of reactor building sump water processed through the SDS system as of October 22, 1981, is approximately 115,000 gallons. Processing of batch number 8 commenced on-.
October 23, 1981.
On October 21, 1981, a dewatered SDS zeolite vessel loaded to j
appr oximately 25,000 Ci of Cs-137 and approximately 1,000 Ci of j
Sr-90 was placed in a shipping cask and removed from the.oent fuel t
pool in which the SDS is located.
A radiation level survey was taken of the cask to verify predicted radiation levels to assure compliance with transport regulations.
Preliminary evaluations indicate that the empirical (test) data confirmed analytical i;
oredictions.
After the radiation level survey the vessel and cask were returned to the spent fuel pool.
2.
EPICOR II.
Processing of the SDS effluent through the EPICOR II system continued this week.
As of October 22, 1981, approximately
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110,000 gallons of reactor building sump water had been polished.
2 Liners F-6, F-7, K-2, and 2 K-i were replaced by. fresh liners.
Liner K-1 was shipped to Richland, Washington for disposal at a commercial burial facility.
3.
Reactor Building Integrity Assessment Program.
Analyses results nave been received from grcund water samples which were taken at the various site ground water monitoring locations during the month of June 1931 and on July 1,1981.
The sample analyses indicate that the activity in the latest samples is within the range of values identified during the course of the sampling program which began in early 1980.
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. The latest analyses indicate that tritium concentrations in the East Dike Catch Basin and in the test borings have remained slightly above background.
Test Boring 2 has historically shown periodic positive indications of minute quantities of cesium. The highest cesium concentration detected in a sample taken in February 1981,was approximately 370 pdi/L of cesium 137.
The most recent gamma scan of water from lest Boring 2 (sample taken September 2,1981) indicates a 8 12 + 4.41 pCi/L concentration of cesium 137.
4.
Reactor Build _ing Entries / Decontamination Experiment.
The. licensee has planned 17 reactor building (RB) entries which are scheduled to commence during the last week in October and continue through November and December. The objective of the 17 entries is t cquire generic research and development information on accident r lated contamination problems.
The initial entries are planned o thoroughly characterize the RB contamination and the contamination ihduced radiation levels on the polar crane and on the two accessible floors of the RB.
Following the characterization, the areas will ba decontaminated to remove loose surface contamination using water with various combinations of temperature and pressure. Follcwing the decontamination experiments, the RB will be resurveyed'to determine the effectiveness of the decontamination techniques. The contamination characterization surveys will include sample removal for laboratory analysis, multichannel analyzer surveys inside the RB, and air, water and area radiation surveys.
The predecontamination surveys will be performed in October and November.
In parallel with the characterization surveys, decon-tamination hardware will be installed in the RB.
The installation will include RB penetration modifications to insert high pressure water hoses into the RB.
A power lift will be attached to the polar crane for use in transporting personnel and equipment from the 305' elevation to the 347' elevation and to the polar crane.
A 10,000 PSI, P5 GPM water pump and water heaters will be installed
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outside the RB.
i The actual decontamination inside the RB is scheduled to commence on the 305' elevation in early December.
The decontamination techniques will be limited to high pressure water sprays and low pressure water washes. Water temperatures up to approximately 140 degrees F. will be used.
It is estimated that the decontamination experiment will add approximately 55,000 gallons of previously processed water to the RB sump.
The SDS system will reprocess this water from the RB sump.
. Public Meetings.
1.
On Wednesday, October 21, the NRC's Advisory Panel for the Decon-tamination of Three Mile Island, Unit 2, held a public meeting at the Hotel Yorktowne in York, PA.
Chairman Minnich and Mr. Roth briefed the panel on the testimony presented on October 21, 1981, joint hearings of the Senate Energy and Natural Resources and Environmental and Public Works Committees concerning the Unit 2 cleanup financial situation.
At the hearing Governor Thornburg, DOE Secretary Edwards, NRC Chairman Palladino, Mr. Peach of General Accounting Office, Mr. Minnich and utility representatives presented testimony and responded to questions from the Senators.
The Reagan administration announced at the hearing via DOE Secretary. Edwards, and in a letter to Governor Thornburgh, (text attached), that the Administration would request funds from Congress to participate in Unit 2 cleanup activities which are "useful research and development activities of broad national benefit".
These include the following activi ties :
- Clean up the water in the building basement.
- Remove and dispose of abnormal wastes not disposable at commercial sites.
- Remove and evaluate the damaged reactor core.
- Develop special tooling needed for early core access.
- And other appropriate activities consistent with these guidelines.
I Mr. Minnich and Mr. Roth's personal observations were that the Senators appeared favorable to Federal participation provideu' that GPU ratepayers also contributed funds toward the cleanup.
The Panel also heard comments from members of the public and questioned GPU and NRC representatives on various issues regarding funding, safety significance of cleanup delays and the progress on cleanup of the contaminated water in the reactor building basement and core l
temperature variations.
The Panel discussed what action it should take concerning the funding issue.
It was decided that the funding issue would be discussed further at the next meeting.
Future Meetings 1.
The NRC's Advisory Panel for the Decontamination of Three Mile I, land Unit 2 will meet November 16,1981 from 7:00 p.m. to 10:00 p.m.
f in the Municipal Building, 400 South 8th Street, Lebanon.
At the i
meeting, the panel plans to discuss the current status of cleanup l
activities at Three Mile Island.
The meeting is open to the public.
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i Following is the complete text of HARRISBURG (Oct. 20) the letter telecopied last night from Presidential Counsellor Edwin Meese 3d to Gov. Thornburgh:
October 19, 1981
Dear Governor Thornburgh:
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l In response to our meetingtof October 1, 1981, as well I
as discussions with Senator Heinz and other members of the Pennsylvania congressional delegation, the Administration has undertaken a review of its participation in the clean-up of the damaged unit at the Three Mile Island generating y
station.
We agree that the. clean-up. entails a number of useful research and development activities of broad national benefit.
In addition, the Federal Government has unique capabilities for ensuring the safe isolation and disposal of certain-radioactive waste materials at TMI.
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du The Federal Government should limit its participation, however, to those activities that are of gen ~eral benefit or that relate to its unique responsibilities under the Atomic Energy Act of 1954 to ensure safe disposal of nuclear waste.
It would not be approgriate for the Federal Government to j
enter into an open-ended commitment to finance a fixed i
percentage of cleanup coscs or to commit funds without regard to whether.those funds were to be used for one of the two legitimate Federal responsibilities identified above.
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u The President is particularly aware of the need to resolve the apparent impasse that has prevented significant progress in the cleanup of TMI.
For this reason, in February i
of this year he approved a request to the Congress for $37 million for use in a Department.of Energy research and development program at TMI in fiscal year 1982.
The work that will commence'in 1982 is the start of an effort that will continue for the next three' to four years.
DOE intends to provide technical assistance to clean up the water in the building basement; remove and dispose of abnormal wastes not
' disposable at commercial sites; remove and evaluate the damaged rea'ctor core; develop special tooling needed for early core access; and other appropriate activities consistent with these guidelines.
The DOE program is described in
' greate'r detail in the agreements between the department and i the opher parties to the cleanup.
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,6-hi De agree that it would be very helpful to have greater f
certainty concerning the availability of funding for this 1982.
Accordingly, I b__;
NE DOE program in years subsequent to FY intends to request fG wish to assure you that the Presidentfunds in future years,to complete Or from Congress sufficient f~
the identified DOE program of research and development a f~
the program approved by the TMI.
to carry out t
(including FY 1982) as well as a total of $48 million yh President last spring, to complete the b
(including previously appropriated funds) activities initiated under the agreement with EPRI.:
- l As you noted in developing your outline of a plan for the states of New the TMI clean-up, the owners of TMI, end the Federal
-l the utility industry, Jersey and Pennsylvania, Government all share an interest in a resolution of the The responsibility for the financial burdens created by the TMI accident must rest primarily with thoseower from the facility
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problem.
who produced and used the electric gBut to the extent that the
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not the Federal Government.
bear and to the extent that it can support research ofFe
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it can appropriately 4
benefit to the nation as a whole, this point, we should all l
At participate in the clean-up. focus our efforts on getting the clean-up comple l
expeditiously and safely as possible.
As the President indicated to you during your recent p
he appreciates your meetings and telephone conversation,
.g leadership in developing a cost-sharing plan which would break the impasse over the clean-up of Three Mile Island.
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The conditional commitment'by the national utilities in-(
dustry to contribute $190 million to the clean-up pro
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The President appreciates the oppor-to solve this problem.
the industry, and the Congress, y
tunity to work with you, other parties in achieving a resolution to" this situation.
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Sincerely, l
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Edwin Meese, III Counsellor to the President i,
Honorable Richard L. Thornburgh Governor Commonwealth of Pennsylvania 17120 Harrisburg, Pennsylvania
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