ML20080L899
| ML20080L899 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/27/1983 |
| From: | Eddleman W EDDLEMAN, W. |
| To: | Atomic Safety and Licensing Board Panel |
| Shared Package | |
| ML20080L879 | List: |
| References | |
| 82-468-01-OL, 82-468-1-OL, ISSUANCES-OL, NUDOCS 8310030377 | |
| Download: ML20080L899 (5) | |
Text
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UNITED STATES OF AMERICA Sept. 27, 1983 NUCLEAR BEGULATOBY COMMISSION i
BEFORE THE ATOMIC SAFETY AND LICENSING BOARD Glenn O. Bri Dr. James H.ght Carpenter James L. Kelley, Chairman In the Matter of
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Dockets 50 400 OL CAROLINA POWER AND LIGHT CO. et al.
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50 401 OL (Shearon Harris Nuclear Power Flant,
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Units 1 and 2)
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ASLBP No. 82-h68-01
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OL MOTION FOR LICENSE CONDITION ON SPENT FUEL STORAGE AT SHEARON HA9RIS PLANT, by Wells Eddlenan Applicants, in their 9/1/83 Motion for Summary Disnosition of Eddleman Contention 64F (safety of snent fuel s hinping cask nrossure rolief valve),
assert that they (at an unspecified tine) intend to ramove the pressure valve in question, as it is not cualified and they cro not seeking to re-qualify it or any other relief valve, as safe for opant fuel shipping use.
They also assert that they will not use casks contkining such a relief valve for snent fuel shinments to Harris, and cnticipate only "drry" (in-air) shipments to Harris for the foreseeable future.
They assert that such are facts about which there is no dispute.
Therefora, I am willing to withdraw Eddlenan 6kF provided the Board will cimnly hold them to their word and innose the following license conditions on storage and possession of spent fuel from other nuclear plants at Harris:
1.
No spent fuel shall be shinped to or from Harris in any cask which uses a pressure relier valve containing Rulon components, such as tho Target Rock 73-J,
- 2. No spent fuel shall be shinped to or from Harris excent as a
" dry shipment", i.e. one cool enough to travel with no more that 1 ft3 8310030377 830927 PDR ADOCK 05000400 Q
2 of water in the spent fuel containing cavity.
The above conditions are reflective of CP&L's asserted intent to only ship dry and not to use the Target Rock valve, and disnose of the material (Rulon) that discovery reveals to be at issue in Eddlenan 6hP.
Since the above safety conditions satisfy the concern admitted into this proceeding in Eddleman 6kF, it is apuronriate to withdraw the contention if such conditions are both imnosed.
(This is not at all to say that I believe such spent fuel shipments are safe or adeountely safe.
But the c ontention is all I am allowed to use in this nroceeding. )
While the above withdrawal would noot Anplicants' motion for Summary Disnosition on this safety contention, sunnary d isnosition should not be granted without such conditions, as they would nerely hold Anplicants to an enforceable connitment to do what they have said they would in their notion for sunnary disnosition.
Therefore it is annropriate that the above Motion be granted and the requested license conditions be inposed on CP&L and its co-Apolicants in this proceeding.
//]
Wells Eddleman t
- While for legal nurcoses under 10 CFR 2.7h9 any fact not contra-l dicted with evidence in a motien for sunnary disnosition is drened to be admitted, it should not be inferred that I adnit that anything CP&L asserts is actually a fact. This notion would, if granted, make CF&L's statement of facts,other than those contaf ned in the license condition above, irrelevant to this case. Therefore I have not out extra energy into refuting their other asserted " facts" with evidence, thoegh I believe a good bit exists.
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Akh 23 i
Radiation Doses from Radioactive Exhaust Air
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ADtmTs (All values in area /yr) whole bcdy thyroid kidney bone noble gas radiation 31 31 31 31 ground radiation 15 15 15 15 total of various food-stuffs 784 809 10,872 4,820 wine 110 96 1,383 937 Total 940 951 12,300 5,803 maxiana value in accordance with section 45 of the Radiation Protection I,aw 30 90 90 180 l
3abies (only iodine-131 l
thyroid cow's milk 753 goat's mil.k 2,204 sheep's milk 2,501
- saxt: sum value in accordance with section 45 of the Radiation Protection *,aw 90
-113-l
t i
Dispersion Characteristics in the Lee of Complex Structures
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1 j
Richerd H. Thuliller Pacific Gas and Electric Company San Francisco, California i
This paper is directed to those concemed with pollutant espersion in the immediate vicinity 137 m meteorological tower southeast of of structures. Gas tracer date have been analyzed to aseees dispersion characterletics and the plant are within 100 m of the water's j
model performance at two nuclear power plant elles. Reyeselon analysis was used to test edge.
i sonettivRy of ground level concentration to various meteorological parameters and effluent was e p a h S fro se release configurations. Various modele and modelinputs were evaluated against field mea-locations on a structure of complex suromonte. Udar data provided information on vertical as well as hortrontal dispersion. Analysis configuration as indicated in Figure 1.
results indicate that wind speed le a more skillful predictor of ground level concentration than Sulfur hexafluoride (SPs) gas was re-any other parameter avaltable at the two study elles. In general, popular models of dispersion leased from a vent atop the reactor u
a a to m
in the see of structures perform poorty with a distinct trend toward increasing under-prediction y
g yg p_
with increasing wind speed. The usefulness of stability typing is shown to be questionable in was released simultaneously from each view of a high sensitivfty to the scheme used in typing. Site specific studies appear to be In-of three vents on the roof of the turbine dispensible for fearty accurate or even conservative modeling of aspersion In the see of cornpien building at a height of 27.6 m AGL Both structures.
releases were nonbuoyant but had a fi-nite exit velocity ranging from 5 to 10 m/s. Sequential bag samplers were ar.
rayed on each of 3 arcs centered on the reactor vent at distances of 350 m,800 Dispersion in the immediate vicinity of Description of the Field Studies m, and 1500 m. Meteorological mea-buildings and other structures is in.
surements taken at the 10 m and 43 m fluenced by a highly complex field of The two studies treated herein are gas levels on the 143 m tower were selected flow generated by the structure as a tracer studies designated to investigate for this analysis. Concentration data perturbation to the ambient flow field in the dispersion of roof vent effluents in were obtained as hourly averages by gas the boundary layer. The nature of such the immediate vicinity (within I to 1.5 chromatography with a resolution of I flow perturbations has been studied for km) of nuclear power plants. Both part per trillion.
decades in wind tunnels and in field studies involved tracer releases at dif-operatm, elevations on the structures of ferent experimer.ts as outlined in a compre.
Duane AmoH Energy Center (DAEC) g plants; sampling of tracer hensive review by Hosker.1 While the flow structure can be extremely com.
concentrations on concentric are seg.
The second study was conducted plex, models for practical application ments downwind and concurrent mea-during the month of July,1978 at the h ve traditionally followed a simple surement of meteorological parameters Duane Arnold Energy Ceater near concept. The principal approach to the on an upwind tower. The studies were Cedar Rapids, IA, under sponsorship of disp?rsion process has been the deriva.
conducted by the same consulting firm, the Electric Power Research Institute 3 tion of adjustments to the standard using a similar approach in each case.
The plant site is one-half kilometer west Gaussian plume spread parameters a, but differed substantially in the nature of the Cedar River in eastern Iowa. A md a,, to reflect enhanced dispersion :
of the site, the release configuration and 50-m meteorological tower is located,iust the turbulent cavity and wake zones the meteorok>gical conditions involved.
southwest of the plant.
downwind of the structure. While the Both studies were conducted in rela-A single tracer (SFe) was employed niture of perturbed dispersion in the tively flat terrain and together cover a with nonsimultanec is releases from the wake of structures is still rather pocrly wide range of conditions.
reactor vent at 45.7 m AGl. a turbine understood, the pressures of regulatory roof vent at 23.5 m AGL and a release requirement have led to the tentative Mmstone Nuclear Power Station (MNPS) point at grade level as indicated in Fig-cdoption of certain modeling algorithins ure 1. Like the MNPS structure, the by regulatory agencies. It is the purpose The first study was conducted during structure at DAEC was complex. Tracer of this paper to evaluate a number of the the months of October and November, releases were nonbuovant and, except more popular approaches to modeling, 1974, at Millstone Nuclear Power Sta-for the reactor vent releases, were using data bases from two recent field tion in Waterford, CT, under sponsor-without appreciable momentum. Reac-experiments. It is hoped that this eval-ship of the Atomic Industrial Forum.2 tor vent releases were made with exit urtion will aid in the interpretation of The plant site is on the south shore of velocities on the order of 8 to 10 m/s.
results under practical application of the the State of Connecticut at the tip of a Zine oxide smoke was released simulta-models.
small pemnsula jutting southward into neously with each release of SFe at the the eastern mouth of Long Island identical release points to assure com-cerW IN2-A r Pollution control Ansonatson Sound. Both the plant structure and the plete mixture with the SFs gas. Se.
526 Journal of the Air Pollution Control Association
Canecntrations in PPM (UG/L)
Supplem:nt to discovary rasnonse on Eddicman 83/8!t Metals Found in Haw River Near Bynum, NC Source: NC Division of Enviro. Mgt connuter records, 5-2[-82 nrintout at page 20 et seq -- conies made avaiable to C.A. Barth NRC who will seed a copy to H. Carrow of CP&L Pollutant DATES of SAMPLES 6/16/81 2/18/8.1 6/11/80 Q
""3 ""4 NTT 5K 220
.50
/
N
/NO 1.7 K 98 23 2
Arsenic 10 K 10 K 10 K Cadmium 50 K 50 K 50 K Chromium 50 K
$0 K
$0 K Cobalt 100 K 100 K 100 K Cooper 40 K 40 K 40 K Iron 1200 1000 1800 Lead 100 K
$0 K 100 K (4/11/80)
Manganese 230 90 120 Nickel 100 K 100 K Zinc 50 K 50 K Marcury 0.5 K 0.5K 0.7 The Haw River feeds the Jordan Lake just above the dam which is some miles above the SHNPP cooling lake outlet into the Cape Fear.
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