ML20031D572
| ML20031D572 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/29/1981 |
| From: | Bell W CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), NUS CORP. |
| To: | |
| Shared Package | |
| ML20031D553 | List: |
| References | |
| ISSUANCES-OLA, NUDOCS 8110130454 | |
| Download: ML20031D572 (68) | |
Text
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r 49 TESTIMONY OF WILLIAM H. BELL CONCERNING RADIATION DOSE RATES ON THE OUTSIDE OF THE SOUTH WALL OF THE SPENT FUEL POOL My name is William H. Bell.
I received my Bachelor of Science Degree in Chemical Engineering from West Virginia Institute of Tc; hnology in 1977.
I have been employed by NUS Corporation of Rockville, Maryland since December of 1977.
I hold the position of Engineer within the Process Engineering Department.
My resume is attached.
I.
Introduction The purpose of this testimony is to respond to Christa-Maria Contention 2 and O'Neill Contention IIA with an explanation of the calculation performed to determine the radiation dose rate on the outside of the south wall of the spent fuel pocl.
Two cases were considered:
1.
Two rows of fresh spent fuel with only two days of decay time are placed in the fuel racks nearest the south wall.
2.
Same as above, but only fuel wi th one year of decay time is placed in the fuel racks nearest the south wall.
II.
Discassion The point chosen for the radiation dose rate evaluation k
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{9 was the tapered section of the south wall which is thinnest wall section around the spent fuel pool with a thickness of 3.5 feet.
Since it is a well known fact that radiation is attenuated by concrete walls the radiation dose rates at all other points on the outside of the spent fuel pool walls must be less than or equal to the radiation dose rate at this point.
The dose rates have been calculated with the use of the computer code QAD-SQ which is an NUS modified version of the code QAD-P5.
Code QAD-P5 was obtained by NUS Corporation from Oak Ridge National Laboratories ( "ORNL") in 1969.
The code was modified and verified according to NUS quality assurance procedures in effect at that time.
OhD is the generic designation for a series of point-kernel computer programs designed for estimating the cffects of gamma rays and neutrons that originate in a volume-distributed source.
Surfaces, defined by quadratic equations, are used fcr a three-dimensional description of the physical situation.
- Speed, flexibility, and case of use, as well as the ability to mock-up any direct-beam radiation problem, contribute to the utility of the program.
QAD and its derivatives are used throughout the nuclear industry to calculate radiation doses due to distributed sources.
f These codes have been used on numerous submittals which have been accepted by the NRC and its predecessor the AEC.
Therefore the accuracy and reliability of these codes is well established.
[p a
!O Various methods are available for calculating the radiation field outside a concrete shield.
Some of the techniques are simple enough to allow ccmputation by hand.
The approach used in the QAD-SQ code. however, is by its very nature designed to be carried out by digital computer, since it requires thousands cf repetitive calculations.
Kernel methods have the merit of simplicity.
The basis of the method is the physically reasonable premise that the radiation field resulting from a distributed source can be obtained by breaking it up into many smaller sources and evaluating and summing each of their contributions.
The kernel is the function that describes how the detector point is influenced by the unit source point.
The point kernel is the basic approach that is used, making the kernel a simple function of the distance separating the unit source point and the detector point.
The calculation performed to determine the dose rate on the outside of the spent fuel pool was modeled by placing two rows of eleven spent fuel assemblies each next to a wall 3.5 feet thick.
The dose detector point was placed directly on the outside of the wall on the vertical and horizontal center-lines of the group of spent fuel assemblies.
Based on Figure 2-1 of the testimony submitted by Rcger W. Sinderman this calculation is highly conservative since fuel racks will only be placed along l
s v
the eastern half of the south wall and not the western half where the tapered wall thickness is reduced to the minimum thickness of 3.5 feet.
The spent fuel source term photon energy spectrum was obtained from the computer code ORIGEN (the ORNL Isotope Generation and Depletion Code).
This is a widely used code which is known to be accurate.
The complete calculation (NUS file number 5148-PE-A4) is attached to this testimony as Bell Exhibit 1.
III. Conclusions Dased on a wall thickness of 3.5 feet the radiation dose rates resulting from the storage of spent fuel assemblies in the two rows of spent fuel racks nearest the wall with two day and one year decay times are 2300 mR/hr and 37.3 mR/hr respectively.
It is therefore the recommendation of NUS that only spent fuel with decay time of one year or more be placed in the two rows of fuel racks near the tapered area of the south wall of the spent fuel pool.
v 0
WILUAM H. BELL EDUCATION West Virginia Institute of Technology, D.S., Chemical Engineering,1977 EXPERIENCE NUS CORPORATION,1977-Present NUS - Lead process engineer responsible for the development of process flow diagrams and radiation shielding source terms for Enrico Fermi Unit 2 liquid and solid radwaste systems. 9 : em y
backfit involved installation of an extruder evaporator volume reduction system, backflushable etched disc filters, a nd oil removal equipment. Served as project manager on a task to develop the design basis source term to categorize and quantify types, volumes, and activities of low-level radioactive waste for a proposed waste-disposal pilot facility at a major Government laboratory.
Was also lead process engineer on projects involving the control of volatile organic emissions from solid-state component manufacturing facilities; the evaluation of post LOCA in containment hydrogen monitoring and control systems; and the design of post accident high-radiation sampiing systems in nuclear power plants.
Assists in engineering projects involving economic and technical evaluation of solid, liquid, and gaseous radwaste systems and assessments of capital and operating cost factors associated with backfitting augmented systems to operating plants. Responsible for all computer code develop-ment and utilization within the Process Engineering Department, includir.g programs associ.ated with ne utron activation, reactor shielding, decommissioning, a nd investor-owned utility economic analyses.
Prepared process descriptions and developed designs and cost benefit analyses of alternative process systems for volume reduction and solidification of solid and liquid radwaste streams in BWR and PWR nuclear power plar ts for Carolina Power & Light, Baltimore Gas & Electric, a nd the Commonwealth Edison Company. Evaluated cement solidification, asphalt extruder evaporator and encapsulation, fluidized bed dryers, and incinerators. Also performed a radiological environ-mental impact study on the packaging and transportation of low-level radioac*.ive waste to an Illinois disposal facility.
MEMBERSHIPS American Nuclear Society American Institute of Chemical Engineers l
PUBLICATIONS A Waste inventory Report for Reactor andFue/ Fabrication Facility Wastes (coa uthor), prepa red for USDOE Office of Waste Management and ECelle MemorialInstitute Office of Nuclear Waste lsclation Project Management Division, ONWl-2ts, NUS-3314.
o Power Reactor low-Level Radioactive Weste Generation and Waste Management Practices, I
B Evaluation, Report C, Feasibility of Volume-Reduction Processe's (coa uthor), prepared for State of Q
California Energy Resources Conservation and Development Commission, NUS-3183.
r s
On Site low l evelRadweste Management Alternatives (coa uthor), prepared for Atomic Industrial l
V Forum, Inc., NUS-TM-321.
NUS CORPORATION
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CHRISTA-MARIA CONTENTION 3-A.
THE CONTENTION The use of type 304 aus-tenitic stainless steel in i
the new spent fuel storage racks could lead to corro-sion cracking in the pool environment, with a resultant risk co the integrity of the racks and the continued safe storage of the fuel.
J.
R.
Weeks in his July 1977 report on ' Corrosion of Materials in Spent Fuel Storage Pools' has indicated that '[s] tress cor-rosion of stainless steel com-ponents or zircaloy cladding cannot be entirely ruled out t
because of the lack of under-standing of the stress states and the degree of sensitization of stainless steel' (p. 10).
B.
MATERIAL 1 ACTS AS TO UHICH THERE IS NO GENUINE ISSUE TO BE HEARD 1.
Type 304 stainless steel, the material to be used in the propssed spent fuel storage racks at Big Rock Point, is inherently resistant to stress corrosion cracking; however, such material can become increasingly susceptible to stress corrosion cracking as a result of cold work and welding.
l (Affidavit of A.
John Birkle, p. 3).
v~,
me
2.
The effects of cold work can be minimized by avoid-ing bending the material whenever possible and by
_an annealing heat treatment applied to the type 304 stainless steel prior to fabrication.
(Affidavit of A.
John Birkle, p. 3).
3.
The effects of sensitization due to welding can be controlled by the use of welding techniques that minimize the time the weld heat affected zone 0
spends in the 850 F to 1450 F temperature range.
(Affidavit of A.
John Birkle, p.
3).
4.
The effects of stress corrosion cracking on the spent fuel storage racks, as discussed in material facts 1 through 3 above, can be prevented for the Big k Point spent fuel pool by the use of a t water chemistry regime described in the Birkle Affidavit, and because the service tempera-ture of the pool is substantially below the temperature range needed to increase the susceptibility of type 304 stainless steel to stress corrosion cracking.
l (Affidavit of A.
John Birkle, pp. 4-5).
5.
The control of the spent fuel pool environment, as stated in material fact 4, will prevent stress corrosion cracking of the spent fuel storage racks due to tensile stresses.
(Affidavit of A. John Birkle, p. 5).
I
1
' O 6.
Based on material facts 1 through 5 above, the type 304 stainless steel storage racks to be installed in the Big Rock Point spent-fuel pool will not.be susceptible to stress corrosion crack-ing, and the structural integrity of the racks will not be adversely affected thereby.
(Affi-davit of A.
John Birkle, p. 6).
C.
DISCUSSION The Affidavit of Mr.
A.
John Birkle amply demen-J strates that the structural integrity of the spent fuel pool storage racks will not be adversely affected by stress corrosion cracking.
The principal bases for Mr. Birkle's strong conviction stems from the strict water che;.istry and j
1
)
the low service te'mperature at the. Big Rock Point spent fuel pool.
The basis for challenge contained in Christa-Maria j
Contention 3 is a quotation from a report prepared by'J.
R.
Uceks.
Licensee acknowledges that Mr. Weeks is eminently j
qualified as an expert in the field of stress corrosion cracking. - lioweve r, it cannot be stated fairly that the i
Weeks' report raises concerns about stress corrosion crack-I' ing with respct to spent fuel storage racks..The quoted sentence has been taken out of context.
The complete para-graph on page 10 of the report reads:
LO l'
l i
I
~,,. -
_4_
7YY V.
S UMMA_RY_
Significant corrosion of nuclear fuel component. is highly unlikely to occur during storage in fuel storage pools at the reactor sites in periods of upwards of 20 years, provided that the water qual-ity in the fuel storage pools is maintained within specifications, and that chloride levels in the pool water are kept to minimum levels
( < 1 ppm).
Stress corrosion of stainless steel components or Zir-caloy cladding cannot be entirely ruled out because of the lack of understanding of the stress states and the degree of sensitization of stainless steel.
Should such a problem develop on the Zircaloy cladding it would be readily detected by routine monitoring of the fuel pool water for radio-activity.
Should it develop on the stainless stael or Inconel components of the fuel bundles, it would be highly localized and unlikely to lead to significant overall deterioration.
Periodic surveillance of the materials in storage at a number of nuclear utilities is bcing planned under the auspices of the U.S.
Energy Research and Development Adminis-tration.
The second sentence of the quotation was cited as the basis for Intervenors Christa-Maria, et al., Contention 3.
- However, if read in context with the entire paragraph, it can readily be concluded that although Mr. Weeks will not rule out the stress corrosion cracking phenomenon in its entirety, he u
. believes the occurrence of this phenomenon in spent fuel 3
storage pools is highly unlikely, provided the pool water i"
environment is maintained within specifications and chloride levels are kept to a minimum level
(< 1 ppm).
On this latter score, it should be emphasized that the maximum chloride level permitted by the water chemistry specifications for the Big Rock Point spent fuel pool is 40 parts per billion.
No factual issue has been raised by Intervenors Christa-Maria, et al, Contention 3 which controverts the facts established in the Affidavit of Mr.
A.
John Birkle, and accordingly, Licensee is entitled to summary disposition.
on the Contention as a matter of law.
i
. UNITED STATES OF AMERICA g.
V NUCLEAR REGULATORY COMMISSION t
BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In-the Matter of
)
4
) Docket No. 50-155 OLA CONSUMERS-POWER' COMPANY
) (Spent Fuel Pool i ;
)
Modification) 1 (Big Rock Point Nuclear Power Plant)
)
.i >
A.
JOHN BIRKLE l
j.
District of Columbia:
SS I
I, A. John Birkle, Section Head of the Materials Section at Consumers Power Company, of lawful age, being first duly sworn, upon my' oath certify.that the statements and information contained in the six-page Statement concerning Christa-Maria.
Contention 3 and the attached resume are true and correct to the best of my knowledge'and belief.
Executed at Washington, D.
C.
/
A
/ l AU S
}
v Subscribed and oworn to. before me this 28th day of Septem'..er, l'181.
i k
&WA f
Notary Public in"and'for % p V
the District of Columbia i
l My commission expires hiy, Cm..w. qm.byr f, h, E
4
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