ML20091D153
| ML20091D153 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 04/29/1969 |
| From: | Melehan J WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20091D132 | List: |
| References | |
| FOIA-91-17 WCAP-7219-L, WCAP-7219-L-R01, WCAP-7219-L-R1, NUDOCS 9108120379 | |
| Download: ML20091D153 (10) | |
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3 NES < Class 2 95 ADDENDt3 TO SAXTON CORE II1 LICENSE APPLIC/ TION 5> 0' ~~ ' h h by J. W. Meichan April 29, 1969 Work Perf ormed Under S.O. IK;RT-303 APPROVED: ~
R. S. Miller, Manager Irradiation Technology 57ESTING110USE El.ECTRIC CORPORATION Nuc1 car Energy Systems P. O. Box 355 Pittsburgh, Pennsylvania 15230 9109120379 91070D POR i OI A DEKOK91-17 Puig
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In accordance with Westinghouse Atornic Power"Ti isions,,proced. surearq.
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ADDENDtN TO SAXTON CORE III LICENSE APPLICATION Introduction This addendum to the Sexton Core III Safeguards Report contains proprie-tary information on load follow fuel rod design which amplifies the de-scription of those rods in the main body of the 'eport. The types of ex- 1 perimental fuel rods and the ranges of rod design values are given here.
The calculational basis for nuclear and thermal-hydraul) designs is dis-cussed in full in the safeguards report and is not repeated here. Me-chanical design, with the exception of a detailed listing of fuel rod variables, is covered in the main report; only a brief description of as-sembly_ design is repeated here. An evaluation of thermal-hydraulic and mechanical performance of these test rods which confirms that a 1 test rods satisfy the applicabic design criteria is summarired in this report. __
The six rods (of the 120 load follow rods) which contain pressure control devices are designed such that internal pressure may exceed primary system pressure et the end-of-life. These rods were analyzed to assure that the clad stress and strain design criteria are satisfied.
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Test Objective and Mode of Operation The objective of the load follow experiment is to determine the effect of fuel rod linear power level, fuel density, fuel-clad gap and internal pres-sure on fission gas release, fuel swelling, and clad strain behavior under power cycling conditions. The study includes combinations of rod design variables representative of both current and developmental fuel designs.
Throughout Core III operar n .he assemblies vill be subjected to several power cycles each day. The lower limit of the cycling range may be re-1
st ricted by Saxton plant capabilities, but is expected to be in the vici-nity of 40% of fall power. The upper limit of the cycle vill bu limited to 100% of full power, as defined in the safeguards report. Iu addition, mid-way through Core !!! 11(c the positions of these two assemblies will be interchanged to simulate power letsi increases associated with fuel management techniques which tre movement of f uel assemblies from low power cere regions to high pow sre regions.
Load Follow Assembly Design The load follow assemblies are similar in design to previous Saxton as-semblies. Tte arrangement of fuel rods and other fuel bundle components of the assemblies is shown in cross section in Tigure 1. Three tie rods hold the 'ranovabic top nozzle in places Two tie rods are Inconel-filled stainless steel tubes and the third tie rod is a stainless steel tube vith a stainless steel filler rod. Five water-filled tubes are used to increase the water-fuel ratio in the center of the assembly and thus in-crease the power level of the adjacent fuel rods.
Tuel Rod Design A number of combinatiocs of the variables listed in Table 1 are included in the 120 fuel rods comprising the two load follev assemblies. The majority of the rods are Zircaloy-4 clad. The several stainless r.cel .
rods are included to study fissior, gas release and fuel swelling with minimized sensitivity to clad-pellet gcp conductance. Six pressurfred rodo contain pressure control chambers located in the top plenum bpacc to limit the range of internal gas pressure from beginning to end of core life. The chambers consist of stainless steel belov vith brated thin diaphragm end closures designed to rupture at internal pressures not to e, m ad-2800 psi. The rods v!th pressure control chambers will operate > peak linear powers in the range 14.5 to 19.9 kv/ft.
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9 Solid Zirca-loy Bar 304 SS Tie Rod With inonel Filler INr Water Vater Filled Filled Zirca- Zirca-loy Tubo loy Tubo Water '*
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Water Water Filled Filled 304 SS Zircaloy
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304 SS 304 55 Tie Rod Tie Rod With incc nel With 304 SS Filler Rc d Filler Rod Solid Solid Zircaloy Zircaloy Bar Bar i
Figure 1: Schematic Diagram of Load Follow Assembly Cross Section Showing General Arrangement (All positions not otherwise noted are occupied by fuel rods.)
NOTE A: In fuel assembly $03-18-3 this position occupied by a Zircaloy tube test specimen assembly at beginning of Core III. In fuel assembly 503-18-1 this position occupied by a flux monitor thimble at beginning of Core III.
Positions of tube test assembly and ilux monitor thimble are reversed in second half of Core III lifetime.
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LOAD FOLLOW TEST ROD DES!CN VARI ABLES i ;
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A. Fuel Composition - 002 [
Density - 89.$% T.D. - 42 rods f 92% T.D. - 42 rods !
94.5% T.D. - 30 rods l
.f-Mixed 89.5% T.D. and 95% T.D. - 6 rods Enrichment - 9.5% U-235 - 34 rods '
12.5% U-235 - 86 rods ,
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- B .~ Cladding 21rcaloy-4 - .3445" 1.D. x .3910" 0.D. [
F 6 rods in recrystallization annealed condition 96 rods in stress-relief annealed condition Type 304 Stainless Steel .361" 1.D. x .391" 0.D. - 18 rods C. Fuel Clad Diametral Cap
- 5. 5, 7. 5, 9. 5 mils for Zircaloy clad rods 3-10 mils for stainicas steel clad rods ;
D. Fuel Rod Internal Atmosphere air at 15 psia helium at 200, 350, 500 paia
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ruel Rod Performante r All of the Load Follow test rods vere designed to avoid fuel meltics, The highest temperature (4600'F at beginning-of-life approximately 500*r below g
the melting point) will occur in a Zircaloy-clad rod at peak design power of 19.9 kv/ft with 89.5% T.D. fuel, an initial pressure of 15 psia . air. 3 With continued irradiation, fuel thermal expansion,and clad creep down tend to increase the fuel-c1cd gap conductance and ti.erefore decrease the fuel >
temperature. Other design combinations were evaluated for initial internal gas pressures up to 500 psia, fuel density up to 94.5% T.D. and fuel-clad gap up to 9.5 ' tis. Because of the higher fuel-clad gap conductance re-sulting from t i higher pressure and because of the higher thermal conduc-tivity of the ,h her density fuel, peak fuel temperatures were predicted to be less than in the case stated above.
The highest internal gas pressure conditions will exist in Zircaloy-clad rods containing pressure control chambers: in several of these rods pres-sure will exceed coolant pressure. llowever, even in the event that the pressure chambers fail to rupture as designed, the clad stress will still be considerably below yield stress and total clad strain will still be 1ess than 1%.
For the Zircaloy clad rods which do not contain pressure control devices, the lead rod end-of-life internal pressure will be less than the 2250 paia primary system pressure. The lead rod design parameters are 89.5%
fuel density, 500 psia initial internal pressure, and 9.5 mil initial fuel-clad diametral gap. At the design peak burmup of 21,000 MWD /MTU, fission gas release is expected to have a minor ef f ect on the total inter- 1 pressure. liigher fuel density and smaller fuel-clad gaps are more moder-ate design combinations leading to increased fuel-clad gap conductance, lower fuel temperatures, lower fission gas release and lower end-of-life pressure. In none of these temperature and pressure Ifmiting combinations does the total clad strain exceed the design limit of 1% in the Zirealoy clad fuel rods.
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1 The questione of fuel t(uperature and internal pressure are also con-sidered for the 18 stainless st eel-clad f uel rods in these two asstub11es.
The tembinations of gap, f uel density and linear power have been chosen to avoid fuel melting and end-of-lif e internal pressures exceeding cool-ant pressure in the stainless steel rods. The higher strength of the stainless steel cladding assures that clad strain at end-of-life vill be less than 1%.
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D.1vid Dekol. ;
I 1,1 Conor Street llarrisburg, Pa 17104
,lan 1,1001
. f REED 0',1 Of IIH0 mil 0fl Mr. Ik>nnie 11. Grimsley Director ACT REQUEST Division of Freedom of Information and Publications Services 0:The of Administration and Resources Management g[MQ"90 f./-9//I Nuclear Regulatory Commission Washington, D C. 20$$$
Re: Freedom of Information request
Dear Mr. Grimsley:
Pursuant to the Freedom of Information Act,I would lite copies of the following documents'
-All documents pertaining to the Ad Hoc Committee for Cooperation fletween the AEC and the Electric Power Industry, which was in existence from 1949 to 1951 Edward W. Morehouse. vice president of General Public Utilities, was one of three members of this committee. If any of these documents are already in the ic<al public document room in llarrisburg. please provide me wish their titles and fiche numbers.
- All documents swith the exception of those provided in a previous Fot A) between 1951 and 1966 inclusive. pertaining to Atomic Power Development Asscciates, an industry consortium organized in 1951 by Walker Cisler of Detroit Edison and of which General Public Utilities was a member.GPU vice president Edward W.
Morehouse was a member of the APDA board and chairman of the Economics Committee. APDA's purpose was to do engineering and economic studies of nuclear energy, and its engineers lloaned from GPU and othersi developed plans for the Enrico Fermi breeder reactor.
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11 any of these documents are already in the local public document room in liarrisburg. please provide me with their titles and fiche numbers The PDR staff has informed me, however, that no APDA documents are in the public dccument room.
-All documents from Jan 1.1955. to Dec 31,1958. pertaining to the hianila Nuclear Power Project of General Public Utilities. The project was a study of whether it was feasible to build a nuclear reactor for hianila Electric Co. in the Philippines, then a subsidiary of GPU, and Atomic Energy Commission personnel were extensively consulted on the project, according to one document I have. If any of these documents are already in the public document room in liarrnburg, please provide me with their titles and fiche numbers-
-All documents not already in the public document room that pertain to the Salton Nuclear Experimental Corporation reactor operated by Westinghouse and General Public Utilities at Saxton, Pa, The time period ir Jan 1.1957 through Dcc,31.1967 I have a print-out of PDR dc<uments on Sarton, and only a handful are dated prior to 1%9 Planning for Salton began in 1957 or 1958
- All corporate documents -for example, corporate board minutep of General Public Utilities. Jersev Central Power & Light Co.. and hietropolitan Edison Co that are in the possession of the Nuclear Regulatory Commission, including those obtained for use in any of the investigations of the Three hiite Island nuclear accident. If any of these are already in the lceal public document room in liarrisburg, please provide me with their titles and fiche numbers.
--Any documents in NRC files that were obtained from the Pennsylvania State Police for use in any of the investigations of the l Thil nuclear accident. This would sclude the State Police helicopter pilot log and the State Police dispatcher hig, both of which were requested from the state by Deputy Director James hl. Allen in a June 28,1979 letter to Lt. Gov. William Scranton of Pennsylvania. If any of
! these documents are already in the local public documents room in liarrisburg, please provide me with their titles and fiche numbers l
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4 The state police refuse to release any of their dc<uments,on any l topic. and are not subject to Fot A or the state's limited Open Records !
Act. If the NRC has any of these documents,it is my only realistic '
source for them 1
Pursuant to the Freedom of information Act. I also request both I representative of the news media status and a public interest waiver of all search and copying fees A publicinterest waiver of search and !
copying fees has been provided by llugh L Thompson Jr., deputy executive director for nuclear materials safety, safeguards and operations support in connection with previous FOI A requests for this !
research project I will now provide the information requested of fee waiver applicants in 10 CFR 9.41(blic) & (dL (1) Describe the purpose for which the requester intends to use the requested information. ;
The dc<uments will be used in preparation of a definitive history of General Public litilities IGPlh, the Three Mile Island nuclear accident and its impact on the world (2) Explain the extent to which the requester will extract +
and analyze the substantive content of the agency record.
1 will provide a great deal of analysis to the information in the documents I obtain from the NRC. I will match it with mlormation I obtain from other sources,like personalinterviews, and use all that information to write a comprehensive, truthful and objective book that will (l1 tell the history of the commercial nuclear industry.
especially the involvement of GPll, before TMl;(2) tell what happened during the TMI accident in 1979;(3) tell what happened during the 10 years af ter TMI (such as the clean up at TMl, the financial problems of the nuclear mdustry,etc.h and (4)willlook at the future of nuclear power in light of concerns over global warming.
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(3) Describe the nature of the specific activity or research !
in which the agency records will be used and the :pecific j qualifications the requester possesses to utill:.e information :
for the intended use in such a way that it will contribute to public understanding. :
i i plan to use the NRC records to write a definitive history for the l general public of the Three Mile Island nuclear accident of 1979 and !
Its impact on the world. The book will describe the events leading to !
the accident, the accident itself, and what happened at TMI and to the ;
nuclear industry in the 10 years that followed, and what the future ;
might hold for nuclear power in light of concerns over global warming. i i
I have considerable experience 'in making compleI scientific or technical stories accessible and interesting to the general public. My first book. Ihseen D.tnser: A Trase& WPeople. Gwernment .indthe l
Centr.th> Jhne/#e (University of Pennsylvania Press 19861 required me to make a complex geological problem understandable to people .
who were not,in most cases, geologists or scientists. The reviews my l hook received testify to my success in carrying that out.
I covered the nuclear energy beat for Ihe Patriot Ns1in Harrisburg for about two years (until GPU Nuclear succeeded last February in having me removed from the beat because 1 am writing this book an arbitration ruling in my grievance is pending) and
, acquired a working knowledge of nuclear terminology and procedures. ;
if there was something i did not understand about something I had i read, I would call an expert who could help me. I would do the same tf there was something I did not understand in the documents I seek in ,
this Fol A request, l
l (4) Describe the likely impact on the public's understanding of the subject as compared to the level of und *rstanding existing prior to disclosure. !
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No comprehensive, definitive history has been written of the TMl accident that includes all the important events that preceded it as well L.._ - .~. _ . , _ . . _ _ , _ _ _ . _ - ,-._ _._ _ _ , . . . - - - - _ , , -
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as wh.it happened to GPU and the rest of the nuclear industry in the years that followed.
My boot will be more than just a simple retelling of the TMl accident. I will place the accident in the context of the rise and Iperhapsi f all of the commercial nuclear industry in the U S and the world.
I intend for my b(ot to be the one people pick up at the library in years to come when they want to know the who what why-when-where and how much of one of the more significant technical. business and historic events of the late 20th century, it will distill the important information from the tens of thousands of government dxuments pertaining to TMl technical papers written by scientists.
and the many other sources of information into one good book (5) Describe (lic site and nature of the public to whose understanding a conitibutions will be made.
This book is being written for the general reading pubhc--the average man or woman who doen not work for the NRC or the Department of Energy or the nuclear industry and who typically would only receive information about IMI from a book acquired at a library or bootstore. I would estimate this to be quite a large, diverse group (6) Describe the intended means of dissemination to the public.
A book.
(7) Indicate if public access to information will be provided free of charge or provided for an access fee or publication fee.
Readers will be able to borrow the book free of charge at public hbraries
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-(8) Describe any commercial or private interest the requester or any other party has in the agency records sought.
I have no commercial or private interest in the NRC documents sought in this request. They will be used exclusively for research for !
my book and will not be sold. ;
(d)(1)llow the subject of the requested agency records concerns the operations or activities of the Government.
It has been the duty of the NRC, and the Atomic Energy Commission before it to regulate the U S nuclear industry, a duty that includes investigation of nuclear accidents.
l (d)(2)llow the disclosure of the information is likely to contribute to an understanding of Government operations or activities.
The documents will be used in a book about General Public Utilities. the TMl accident. and its impact on the world Readers of the book will come to understand the role of the NRC and the AEC before ;
it. in supervising the U.S. nuclear industry, and of the AEC in promoting the U.S. nuclear industry. ,
(d)(3) If disclosure of the requested information is likely '
to contribute to public understanding.
To the best of my knowledge. no definitive history has been written about the TMI accident, and none of the books that have been i written fully describe the history of GPil s involvement in nuclear energy.
(d)(4) If disclosure is likely to contribute significantly to public understanding of Government operations or activities.
The docunients will contribute significantly to a general public understanding of the_ role of the AEC in regulating and promoting 1
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i nuclear power and of the NRC in regulating it. Relatively little has ,
been written by non-government sour:es about the early history of t commercial nuclear energy, and to the best of my knowledge, nothing has been written for the general public about GPU's early involvement l with nuclear energy Thus, the requested documents will make a l significant contribution to public understanding. The corporate ,
i documents will contribute to public understanding in the same manner. As for the state police documents. they show the range of :
areas investigated by the NRC after the nation's worst commercial -
nuclear accident.
(d)(5) If, and the extent to which, the requester has a i commercialinterest that would be furthered by the disclosure of the requested agency records.
l anticipate receiving royalties on the book, perhaps in four or five years. llowever, there is no guarantee I will make any profit on the book,it is often said that most authors would make more money by spending the same amount of time working in a fast food restaurant. ,
My first book, Unseen Danger, received f avoracle reviews, including one in The New York Times was purchased for many libraries and earned me enough to buy a nice topcoat. which I still have but which is starting to show its age, I hope this book will do better, but one never knows.
(d)(6) If the magnitude of the identified commercial interest of the requester la sufficiently large, in comparison with the public interest in disclosure, that disclosure is primarily in the commercial interest of the requester, i
As I have stated, the documents will be used in a def mitive history of the TMI accident and its impact on the world, I anticipate receiving royalties, but i believe the public interest in disclosure of the. t L documents clearly outweighs any minimal commercial benefit to myself.
- The public has an especially significant interest in this issue because of the global warming problem. Nuclear power production -
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emits only a tiny fraction af the carbon diotide emitted by a onventional power plant t urning fossiliveli. Mi and the nuclear /
safety issue re:nains a roadt lock in the public mind to greater use of nuclear pcwer, however, and ualess the public is given all the facts, about issues great and stnall. it cannot make an talormed decision.
Thank you for your considera$ ion
_ Sincerely, ,
- k. . '~ ) ' , fif David DeLot O
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David Dellot 113 Coney Street llarris burg. Pa.17104 Jan8,1991 Mr Ibnnie 11 Grimsiey Director Division of Freedom of Information and Publication Services Office of Administration and Resources Management Nuclear Regulatory Commission Washington.DC 20555 Re Amended fol A request Dear Mr Grimsley I wish to make a slight amendment to one of the categr. ries of documents 1 atted for in my FOI A request of Jan I,1991 in the paragraph that asked for All documents not already in the pubhc document room that pertain to the Salton Nuclear Experimental Corp reactor operated by Westinghouse and General Public Utilities at Salton. Pa , ~ please de;ete the time p. riod for the requested documents.jan.1,195?. through Dec. 31,1967.
I now wish to obtain copies of all Sarton related documents dated Jan 1.1957 through Jan I,1991, that are not in the pubhc document room.
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David M.'ok l
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