ML20003H950
| ML20003H950 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/04/1981 |
| From: | Hovey G METROPOLITAN EDISON CO. |
| To: | Snyder B Office of Nuclear Reactor Regulation |
| References | |
| LL2-81-0096, LL2-81-96, NUDOCS 8105080229 | |
| Download: ML20003H950 (6) | |
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o Metropolitan Edison Company Met-Ed GPtl
~" o* a "8o Middletown, Pennsytvania 17057 Writer's Direcs Dial Nurneer May 4, 1981 LL2-81-0096 eA ik g
TMI Program Office Attn:
Dr. Bernard J. Snyder, Director l9 9g QT NO7 U. S. Nuclear Regulatory Commission os*A888 j1
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Washington, D.C.
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Dear Sir:
g Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 EPICOR -II Prefilter Disposal The purpose of this letter is to set forth our conceptual plan for disposal of EPICOR-II prefilter liners. Your review will permit us to firm up our plans for these liners.
Our plan is to dispose of these liners in licensed commercial burial grounds. Disposal will be in accordance with burial ground require-ments and in accord with the limits defined in the latest draft of 10CFR Part 61, dated November 5, 1979, in our possession (and as these limits are developed in NUREG/CR-1005*).
To ensure compliance with burial ground requirements, we will again dewater the liners prior to shipmcat, if necessary. Additionally, we will encase the liners in high integrity containers (HIC). We intend to use containers which comply with the design requirements being used by the Department of Energy (DOE) in the development of HIC. The criteria being used are intended to meet burial ground requirements. The criteria are set forth in Sandia Laboratories Report SAND 81-0567. TCC-0198, UC-71, dated March 1981. The basic criteria have been extracted from the report and are included here as.
These criteria are amended by Attachment 2, a letter from H. M. Burton to W. W. Bixby, dated April 16, 1981.
These liners will be buried in the same manner as the second and third stage EPICOR-II liners, described in oor letter, LL2-81-0091, dated April 3, 1981. Burial will be in a slit below the bottom of the usual 30-foot deep trench.
OD!
If buried as described above, strontium is the controlling nuclide for these liners, as identified for waste class B in Table E.A of J
l NUREG/CR-1005. As such, the limits of NUREG/CR-1005 (page XIV) would II
- NUREG/CR-1005, "A Radioactive Waste Disposal Classification Syscem" O
8105080 l
Metrocoitan Ecson Comodny is a Merrcer of the General Pubte Lwes Sys*em l
5 Dr. Bernard J. Snyder LL2-81-0096 3
apply. For Sr. this limit is given as 38 pCi/cm. However, the test of the report states that the Sr limit for Class B wastes is -
related to the Sr limit fog Class C wastes by a 150 year d g. There-fore,gnsteadof38pCi/cm,thevalueghouldbe2.4+0.5 g
= 97.2 pCi/cm (2.4 150the Class C limit for Sr., 5.34 is the number of half-lives of Sr in 150 years). We have calculated that the total 90 inventory of Sr in all 50 EPICOR-II prefilters is 761 curies (conserva-tively assuming all strontium removed for the Auxiliary and Fuel Handling Buildingisjntheseliners). Thiscalculatedgoanaverageconcentration of 18 pCi/cm, with a ra e of 6.2 to 88 pCi/cm. All values are below the limit of 97.2 pCi/cm Due to the limits on transuranics for shallow land burial, the TRU content of each prefilter will be determined.
If any liners exceed the existing limit of 10 nCi/gm, burial in a commercial facility is not permissable.
Under these circumstances, it is assumed that ultimate disposal would be to a ultimate disposal location, probably a geological repository, when such is established by the Federal Government.
Interim storage until such an ultimate disposal location is available could either be on-site in the HIC's or possibly at an interim storage location away from TMI.
We feel that compliance with burial ground requirements for dewatering and confinement in high integrity containers adequately protects the health and safety of the public now and in future generations. This is strengthened by our compliance with the limits proposed in NUREG/CR-1005.
This NUREG supports the fact that the proposed limits adequately protect the health and safety of the public. Additionally, the NUREG does not take any credit for a container. The planned use of the HIC significantly adds to the prote : ion of the public afforded by the NUREG-proposed (and draft 10CFR Part 61) limits.
For the above reasons, we propose to proceed with the plans discussed herein.
If you wish, we will be pleased to discuss it with you.
Sincerely, G. K. Hovey Vice-President and Director, TMI-2 GKH:RBS:vjf cc:
L. H. Barrett, Deputy Program Director I
l l
ATTACHMENT 1 HIC Environmental Design Requirements I.
HIC External Environment Requirements - the HIC must be designe/ co resist the following external environment conditions 1.
The HIC shall retain all liquids and solids for a 300 year lifetime.
r 2.
The HIC shall be designed for a maximum burial depth of 30 meters.
3.-
The HIC shall be able to withstand a uniform lithostatic pressure of 0.66 MP a (96 PSIG) or stacking load of 0.24 MP a (34 PSIG).
4.
The HIC shall be able to withstand a hydrostatic pressure of 0.29 MP a (43 PSIG).
5.
The HIC shall be designed to withstand a combined uniform lithostatic and hydrostatic pressure of 0.84 MP a (129 PSIG).
6.
The HIC shall be designed to resist external corrosion due to the disposal site environment given the initial soil parameters dis-cussed below:
a.
Ambient soil Temperature HIC design valve: 20 C + 10C b.
Water Content of Soil, HIC design value: 0 to 100%
c.
Oxygen Content. HIC design value: 0 to 3 mg/ liter
]
d.
Chloride content, HIC design value: 0 to 5.1 parts per million e.
pH, HIC design value:
6.5 to 9.0 7.
The HIC shall be designed such that water is r.ot entrapped or retained on its external surfaces.
8.
The HIC shall be designed such that ihe disposal configuration minimizes void spaces which would be difficult to backfill.
9.
The HIC shall be capable of withstanding an internal thermal load of 4 watts in the disposal environment.
II. HIC Internal Environment Requirements - the HIC must be designed to resist the following internal environment conditions.
1.
The initial quantity of free liquid available for contact with the HIC surface shall be less than 1% by volume.
2.
Controlled venting of gases (Tritium. H, SO, CH, NO ) shall be 2
4 designed into the HIC.
3.
The HIC shall be designed c2 resist internal corrosion due to the waste form given the initial parameters below:
l
ATTACHMENT 1 Page 2 of 2 a.
HIC initial heat generation of 4 watts.
b.
The initial gases contained in the wacte form are saturated air, H SO, CH, NO, and CO Thechfo,ridecontentEfthewa$teformrangesfromzeroto 4
c.
i 14 parts per million.
d.
The initial pH of the liquid in the HIC ranges between 2 and 9.
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P. O. Boa 1625 Idaho Falls, Idaho 83401 April 16,1981 Dr. Willis W. Bixby, Manager DOE /TPI Site Office P. O. Box 88 Middletown, PA 17057 HIGH INTEGRITY CONTAINER REOUIREMENTS - Hmb-74-81 o
O Ref.1: Vigil, H.G. and Allen, G.C. " Proposed Design Requirements for High Integrity Containers Used to Store, Transport and Dispoce of High a
Specific Activity, Low Level Radioactive Wastes From Three Mile Island Unit II" Transportation Technology Center, Sandia National e
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Laboratories. Report SAND 81-0567, TTC-0198, UC-71, March 1981.
Dear Dr. Bixby:
Sandia National Laboratory (SNL) was requested by DOE to establish design requirements for High Integrity Containers (HIC) for disposal of high specific activity waste using the EPICOR II prefilters as a design basis.
This effort has been sumarized in Reference 1, and serves as the basis for the procurement specification for the HIC program. However, several changes to the parameters were made, primarily due to infomation developed as part of the EPICOR-II characterization program. This memorandum identifies the changes which follow:
1.
The range of pH in the free standing liquid was changed from 4 to 9 and t
I 2 to 11 in the specifications as suggested by NRC.
2.
The possible range of chloride content in the soil was changed from 0-6 ppm to 0-300 ppm as suggested by NRC.
3.
Freeze / thaw cycling reoufrement was changed from a minimum 10 year period to 60 cycles to quantify the requirement, and to meet the 1 year storage life requirement of 10 CFR 71.
4.
The initial waste fom heat generation rate was increased from 4 watts j
to 8 watts to account for daughter product activity.
I 1
Dr. W.W. Bixby April 16,1981 Hmb-74-81 Page 2 The balance of the requirements in the specification are based on standard practices and procedures for procurement and fabrication of containers including quality assurance and safety consideratf ors.
Very truly yours,
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\\k D,kech',w Harold M. Burton, Manager Technical Integration Office Infomation and Examination Procram C
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