ML20052B690
| ML20052B690 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/09/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-82-020, CON-NRC-TMI-82-20 NUDOCS 8205030457 | |
| Download: ML20052B690 (15) | |
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DISTRIBUTION I
TMIPO HQ r/f TMI SITE r/f CENTRAL; FILE NRC PDR April 9,1982 LOCAL PDR iiRC/THI-82-020 Site Operations File MEMORNIDUM FdR:
Harold R. 'Deriton, Director Office of nuclear Reactor Pagulation
,Q /,_ _. ' ~,.Yg Bernard J. Snyder, Prograu Director 6
THI Program Office h
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Lake H. Barrett, Deputy Program Director
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SUBJECT:
NRC THI PROGRAll 0FFICE WEEKLY STATUS REPORT 4
g s s, y Enclosed is the status report for the period of April 4,1982 to April 9,1982 Major items included in this report are:
Liquid Effluents HRC and EPA Environmental Data Radioactive Haterial and Radwaste Shipments Submerged Demineralizer System Status EPICOR II Reactor Coolant System Water Processing Reactor Building Entries Unit 1 Developments Purification System Filter Shipments NRC-DOE Memorandum of Understanding -
Groundwater Monitoring Status Public Neetings take H. Barrett Deputy Program Director 8205030467 M Program OfH u su S k n eated R11PMh.
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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)
PHS EPA DOE Projects Br. #2 Chief, DRPI, RI DRPI Chief, RI Public Affairs, RI State Liaison, RI DATEf
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o fiF.C iMI FF.0GF.;y. OFFICE WEEKLY STATUS F.EF0F.T e'
April 4, 1982 - April 9, 1982 Plant Status Heat transfer from the reactor coolant system (RCS)
Core Cooling Mode:
loops to reactor building. ambient.
Decay heat removal systerr.s.
Long term Available Core Cooling Modes : cooling "B" (once through steam generator-B).
Standby pressure control (SPC) ' system.
RCS Pressure Control Mode:
Mini decay heat removal (MDHR) system.
Backup Pressure Cont'rol Modes: Decay heat removal (DHR) system.
Major Parameters (as of 0500, April 9,1982) (approximate. values) o Average Incore Thermocouples :
101*F 128'F Maximum Intore Thermocouple:
P,C5' Loop Temperatures :
A B
Hot leg 97.p 100*F 4'92*F 5'F Cold Leg (1) 84*F (2) 91*F RCS Pressure:
104 psig Reactor Building:
Temperature:
63*F Elevation 283.2 ft. (0.5 ft, from floor) o Water level:
Pressure:
.59 psig Airborne Radionuclide. Concentrations.
3 2.0 E-7 uCi/cc H (sample taken 3/31/82) 4.1 E-6 uti/cc Kr85
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(sample taken 3/30/82)
Effluent and Environmental (Radioloaical) Information 1.
Liquid effluents from the TMI site released to the Susqu in accordance.with NRC requirements an'd City of Lancaster Agreement dated.. February 27, 1980.
through April 8,1982', the During the perio'd April 2,1982,
effluents contained no detectabl.e radioactivity at the discharge point and individual effluent sources, which originated within Unit 2, containe'd no detectable radioactivity.
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2 Environmental Protection Agency (EPA) Environmental Data.
The E
'4iddletown Office has not received the environmental Kr-85 analytical results for the samples which were taken March 12, 1982, through April 2,1982, from the EPA's Counting Laboratory at Las Ve.jas, Nevada. When these results become available, they,will be included in a subsequent report.
No radiation above normally occurring background levels was detected in any of the samples collected from EPA's air and gamma rate networks during the period from March 31, 1982, through April 8,1982 3.
NRC Environmental Data.
Results from NRC monitoring of the environment around the TM1 site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
I-1 31 Cs-137 Sample Period (uCi/cc)
(uCi/cc)
H P-314 April 1,1982 - April 7,1982
< 7.2 E-14 <7.2 E-14 4.
Licensee Radioactive Material Radwaste Shipments.
On Wednesday, April 7,1982, one cask (1/2 Super Tiger Protective Overpack) containing Unit 2 make-up system filters and reactor building samples was shipped to the Idaho National Engineering Laboratory, Scoville, Idaho.
On Wednesday, April 7,1982, five liquid samples (various flush r
samples) from Unit I were shipped to the Westinghouse Electric Corporation Laboratory, Waltz Mills, Pennsylvania.
Major Activities 1
Submerged Demineralizer System (SDS)._ The SDS is shutdown for minor maintenance.
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2.
EPICOR II._
The EPICOR II System is shutdown because of lack of water to be processed.
3.
Reactor Coolant System (RCS) Processing.
Engineering efforts are still in progress for processing the RCS.
Fabrication and
' construction efforts are underway for needed har'dware modifications.
The NRC TMI/P0 site office has approved approximately 30 percent of the procedures needed for RCS processing.
The remaining procedures are under r.eview.
The NRC TMI/P0 is awaiting receipt of a request by the licensee to revise the Recovery Operations Plan to incorporate changes to accomodate 'RCS processing.
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4 Reactor Building Entries.
The reactor building entry scheduled for April 7,1982, was cancelled when it was decided to perform minor maintenance and housekeeping on entry support facilities and equipment.
The next reactor building entry has been scheduled for Wednesday, April 14, 1982.
During this entry installation will commence on a pump designed to remove the remaining water (approximately 30,000 gallons) from the basement of the reactor building for processing through the Submerged Demineralizer System.
Work will also commence to remove HPR-214, the reactor building dome radiation monitor. HPR-214 will be shipped off site for laboratory analysis.
5
_TMI Unit i Developments.
The licensee presented plans to the NRC staff for repairing defective tubes in the Once Thru Steam -
Generators (OTSG's) in Unit 1.
The repairs which could be completed in approximately five months will involve both tube plugging and tube rolling.
The tube plugging, which permanently removes tubes from service, could involve up to 500 tubes in both OTSG "A" and "B".
The licensee stated that up to 10,000 tubes could require rolling.
The proposed tube rolling would be completed remotely by either mechanical or hydraulic expansion techniques.
By performing this type of repair these 10,000 tubes will be maintained in service.
The actual tube rolling and expansion may be completed during June through August, 1982.
Upon completion, leak testing and eddy current examinations will be performed.
The licensee also will perform examinations of the reactor coolant system and reactor core internals. The results of these tests will be assessed to insure that other components were not affected by the corrosion probl em.
6.
Purification System Filter Shipment.
Five filters which were removed from the letdown and makeup systems (RCS purification system) were shipped on Wednesday, April.7,1982, to EG&G Laboratories
~1n Idaho for analysis.
The filters had been in the RCS purification system during the accident in March,1979.
7.
NRC-00E Memorandum of Understanding on TMI Wastes.
The U.S. NRC and U.S. 00E agreed to a revision to the existing Memorandum of Understanding (MOU) concerning disposition of solid nuclear wastes from TMI-2 cleanup.
The original M00 was signed July 15, 1981.
R 15, 1982, identified significant changes i,evision 1, signed Marchn the. proposed disposition of the reactor fuel a purification system demineralizer resins..The DOE has agreed that the entire reactor core will be shipped to a DOE facility for selected research and development.
Ultimate disposition will be negotiated between DOE and the owner, GPU Nuclear.
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. The DOE has also agreed to take possession of the makeup and purification system demineralizer resins which will be part of a research and development program.
A copy of the revised MOU was transmitted by Department of Energy Secretary, James B. Edwards, to the Governor of Pennsylvania, Dick Thornburgh, on April 7,1982.
The transmittal also included an Agreement in Principle between DOE and GPU for acquisition of the entire TMI-2 reactor core by DOE.
The DOE will conduct a research and developmeltprogram to examine the damaged reactor core with the objective of gaining additional understanding of degraded core performance and contributing to nuclear reactor safety on a generic basis. A copy of Mr. Edwards' letter, the MOU, and the Agreement in Principle ~ are attached.
E.
Ground Water Monitoring Program.
The analyses of ground water samples taken from on-site test borings in February and March have been received.
The most recent analyses results are shown on.
A sample taken from test boring 17 on March 23, 1982, contained the highest tritium concentration of any sample taken to date (1,100,000 pCi/1).
The previous highest reading for test boring 17 was 678,000 pCi/1, for a sample taken February 25, 1982.
The previous highest reading for any test boring was for test boring 2, with a level of 954,000.pCi/1, -for a sample taken February 12, 1982.
More recent samples from test boring 2 have shown reduced levels of tritium, down to 30,900 pCi/l for a sample taken March 23, 1982.
Test boring 3 has also shown increased levels of tritium, increasing from 2500 to 24,700 pCi/1 for a sample taken March 23, 1982, compared to a March 9,1982 sample.
All of the. test borings that show increased levels of tritium are located near the borated water storage tank.
The aquatic environment
-in the TMI area did not show any apparent increase in tritium concentrations.
The maximum permissible concentration of tritium in unrestricted areas, established by 10 CFR Part 20, is 3,000,000 pCi/1.
No other radioisotopes except tritium were detected in the February and March samples.
The licensee has increased his surveillance frequency of the on-site test borings, and has also instituted a systematic program to identify the source of the tritium.
As a confirmatory measure, the NRC has
,. taken samples from the' test borings and is curre.ntly performing independent analyses.
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5 Future Meetings 1.
On Wednesday, April 14, 1982, Lake Barrett will be the keynote speaker for the Southern Pennsylvania Association of Occupational Health Nurses, to be held at the Holiday Inn in York.
2.
On Thursday, April 22, 1982, the TMI Advisory Panel for the decontamination of TMI Unit 2 will hold.a meeting in Harrisburg at the Holiday Inn located at Second and Chestnut Street, to. discuss the current status of the plant cleanup program.
3.
A meeting is scheduled on April 14,1982, at 7 :00 p.m. between the--
NRC staff and members of Three Mile Island Alert and Newberry Township TMI Steering Committee.
The purpose of the meeting is. to obtain input to the scoping process for the psychological stress related to TMI-l restart.
The meeting will be held at the Newberry Township Hall, Newberry Township, PA.
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$P993 THE SECRETARY OF ENERGY WAS HINGTON, D.C.20La5
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April 7,1982 Honorable Dick Thornburgh Governor of Pennsylvania Harrisburg, Pennsylvania 17120
Dear Governor Thornburgh:
Thank you for your March 11, 1982, letter regarding our mutual discussions about a plan for the Department of Energy to assume possession and responsi-bility for safe disposal of the entire core in the damaged Unit 2 reactor on Three Mile Island.
We appreciate your extensive efforts to facilitate a mutually acceptable arrangement among the Department of Energy, the Nuclear Regulatory Commission., and General Public Utilities.
Enclosed please find a signed copy of a Memorandum of Understanding between the U.S. Nuclear Regulatory Commission and the Department of Energy specify-ing objectives, roles, and responsibilities for removal of the entire damaged core.
Also please find an enclosed Agreement in Principle between the Department of Energy and General Public Utilities for acquisition of the damaged TMI-2 reactor core by the Department of Energy.
These two documents provide a basis for developing the detailed contractual agreements for taking the entire core as soon as it is removed from the reactor.
Thank you again for your leadership in providing a framework for proceeding with the cleanup of TMI-2.
I doubt seriously if we would have accomplished this without your efforts.
Sincerely, r
t' ames B. Edwards F
Enclosures I
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Memorandum of Understanding Between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy Concerning the Removal and Disposition of Solid Nuclear Wastes from Cleanup of the Three Mile Island Unit 2 Nuclear Plant I.
Objective This memorandum of understanding specifies interagency procedures for the removal and disposition of nuclear wastes resulting from cleanup of the Three Mile Island Unit 2 plant. This will help to ensure that the TMI Site does not become a long-term waste disposal facility.
II.
NRC Roles and Responsibilities The NRC has the responsibility under the Atomic Energy Act of 1954 as amended (42 U.S.C. 2011 et seq.), to regulate.all licensee activities at the TMI-2 site, including waste management, and ensure these activities e
are carried out in accordance with the requirements of applicable rules and regulations and the requirements of Facility Operating License Number DPR-73, as modified by amendments or orders issued by the NRC. NRC will carry out its responsibilities by onsite observation of [icensee activities. As required, policy, and technical support will be provided to the NRC TMI Site Office by NRC Headquarters and Regional Office (s).
NRC will work cooperatively and closely with the DOE, and will keep DOE fully and currently infomed of NRC's activities.
NRC will continue to keep public, state and local officials infomed of 1
NRC's activities. When appropriate, NRC will involve DOE in these
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information exchanges with the public, state and local officials.
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III. DOE Role and Responsibiljties Where DOE determines that generically beneficial research, development and testing of the TMI-2 accident generated solid wastes can be carried out, DOE will perform such activities at appropriate DOE facilities. For
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those other wastes that cannot be disposed of in connercial low level waste facilities, DOE may also assume responsibility for removal, storage, and disposal to the extent that the licensee provides reimburse-ment to the DOE. These activities will be undertaken to the extent consistent with appropriate statutory authority.
NRC licensing of DOE facilities that are utilized for storage, processing or disposal of TMI-2 accident generated wastes will not be required since these facilities have primary uses other than for receipt and storage of wastes resul' ting from licensed activities.
The DOE will provide technical support to the licensee and the NRC 'as
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deemed appropriate.
DOE will work closely with the NRC and keep NRC informed of DOE's activities.
l IV.
Currently Identified TMI-2 Accident Generated Solid Radioactive Wastes The followi.ng lists those TMI-2 accident generated solid radioactive wastes which currently exist are planned to be generated. This listing may be modified in the future as the cleanup progresses.
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EPICOR-II System Wastes Forty-nine ion exchange resin liners with loadings up to 1500 curies / liner are in temporary storage at the TMI-2 site. DOE plans to develop a prototype high integrity container (HIC), p'oduction r
units of which, if utilized by the licensee, may allow these liners to be acceptable for licensed disposal in commercial land burial facilities some 1-2 years from now. DOE is also performing characterization experiments on one of these liners and nay fin'd it desirable to extend its R&D program to other liners. Should a more
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expeditious handling of these wastes be required due to the potential for a limited release to the storage environment (which could cause public concern), a contingency plan will be implemented wherein. DOE would at its discretion take receipt of these EPICOR liners on a reimbursable basis from the licensee for storage or disposal.
Future EPICOR-II liners are anticipated to be loaded to allow commercial shallow land disposal offsite by the licens'ee.
- 2. -Submerged Demineralizer System Wastes It is anticipated that.the dispersed radioactivity in accident generated water will be deposited on zeolites in submerged deminera-l lizer system (SDS) liner 3.
Due to the unique character and nature of these wastes, DOE will take possession of and retain these liners to l
conduct a waste immobilization research and development and testing program.
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Reactor Fuel Following removal of the damaged core from the reactor vessel, the entire core will be shipped to a DOE facility to survey and select Information those portions most appropriate for DOE's R&D program.
obtained from detailed examinations is expected to be of generic benefit to design, fabrication and operation.of reactor cores in a safe and efficient manner for current and future nuclear power plants. The remainde'r of the core will remain in storage at the DOE facility and will be ultimately disposed of under an agreement to be negotiated between DOE ani the owner.
4.
Transuranic Contaminated Waste Materials As the cleanup progresses, some waste materials (e.g., sludges) may be found to be contaminated with transuranics at levels above which commercial low level burial facilities are authorized to accept.
Alternatives for such material will be considered on a case-by-case basis and could include archiving, R&D evaluation or temporary storage onsite, or at a DOE facility awaiting further processing and/or disposal in a permanent repository offsite.
Depending on the nature of these materials, DOE's activities could either take~ the form of an R&D program of generic value, or would be subject to reimbursement by the licensee.
5.
Makeup and Purification System Resins and Filters During the THI-2 accident, the makeup and purification system demineralizer vessels and filters were highly contaminated by letdown 1
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5 of reactor coolant through the system.
These resins and filters have not been characterized, however, based on radiation measurements, the resins and filters are believed to have specific activities well in excess of the loadings on the high specific activity EPICOR-II prefilters and are considered unsuitable for commercial land disposal. Due to the generic value of the infonnation to be obtained and the very high specific. activities of the filters, DOE will take possession and retain these filters for research and development activities. DOE will also take possession of and retain purification system resins either for an R&D program of generic value or for storage or disposal on a reimbursable basis.
6.
Other Solid Radioactive Wastes The low-level wastes associated with decontamination (e.g., some ion exchange media, booties, gloves, trash) will be disposed of by the' licensee in licensed commercial low level burial facilities.
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This Memorandum of Understanding will take effect when it has been signed Y.
by tYe authorized representative indicated below for each agency. DOE and NRC shall each have the right with the consent of the 'other party to modify this agreement.
I FOR THE U.S. NUCLEAR REGULATORY COMMISSION FOR THE U.S. DEPARTMENT OF ENERGY W
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Franklin E. CoffmarV '
Bernard J. Snydgy, Program Director TMI Program OffTce Deputy Assistant Secretary for Office of Nuclear Reactor Regulations Nuclear Waste Management and Fuel Cycle Programs Office of Nu lear nergy Date: 7
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81-Date:
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Agreement in Principle Acquisition of the Damaged TMI-2 Reactor Core by 00E Whereas, the Owners of Three Mile Island Nu: lear Generating Station, Metro politan Edison Company, Pennsylvania Electric Company, Jersey Ce Light Company, all subsidiaries of General Public Utili TMI-2 nuclear powerplant in as safe and efficient manner as possible, and Whereas, it now appears likely that shipment of the bulk of the damaged from a public health and safety as well as from a cos
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Whereas, the Department of Energy (DOE) is authori::ed to conduct a resea and development program to er: amine the damaged reactor core so as to enha understanding of degraded core performance and thereby contribute to nuclea reactor safety on a generic basis, and Wherdas, acquisition of the entire TMI core will signific evaluating generic reactor safety matters:
l It is therefore agreed that:
The Department will acquire ownership of the damaged core from the Owners 1.
at no cost to DOE.
The Department will arrange for shipment of the entire core to a DOE Title to, and responsibility for, the damaged 2.
for an examination program.
fuel will be transferred to the 00E upon leaving the TMI site boundary.
The Owners will reimburse cost of shipping to a DOE site.
3.
The Department will fund the cost of interim storage, su 1
4.
I take about 3 to 5 years.
The Owners will reimburse costs associated with storage (beyond the R&D period referred to in item 4) and disposal, up to a reasonable value to b 5.
The cost to be reimbursed shall not exceed that which the Owner would incur in storage of a TMI type core in a TMI-l fuel pool agreed upon.
awaiting ultimate disposition, and for ultimate disposal in a Government repository.
This Agreement is contingent upon negotiation and execution of a written contract between DOE and the Owners, which contract shall define the.
6.
partiplars to a degree satisf actory to all parties.
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On Behalf'of the Department of Energy On Benalf of <tn'e'0wners Witness Governor of Pennsylvania
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