ML19241B485
| ML19241B485 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 05/22/1979 |
| From: | Sekuler S ILLINOIS, STATE OF |
| To: | |
| References | |
| NUDOCS 7907180154 | |
| Download: ML19241B485 (27) | |
Text
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i NRC PUBLIC DOCmENT E0f>M n:LATED CORRESPONDENCE 2:ITIO STATES C7 ' '3 7 7 v A
- 'UCLEAR REGULATORY CCMMIT'iION BEFORE TEE ATOMIC SAFETY AND LICENSING BOARD In the Matter of:
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DOCKET NOS. 50-295 COMMONWEALTH EDISON COMPANY
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50-304 (Zion Station Units 1 & 2)
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ro ESTIMONY OF, GREGORY C. MINOR, cn behalf of the STAE OF ILLINOIS Office of the Attorney General DATED: May 22, 1979 y)l
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TESTIMONY C? GREGCRY C.
MINOR concerning contentions 2 (e),
2(f), 2th), 2(;) anc 4(a).
My name is Gregory C. Minor and I am a partner an MES Technical Associates in San Jose, California. I have had nineteen (19) years experience in the nuclear industry, including design, main-tenance and checkout of nuclear reactor systems, design and testing of safety and control systems for use in nuclear reactors, and the perform-ance of safety analyses for various local, state and national organizati A statement of my background and qualifications is attached to this testimony as attachment I.
The following testimony concerns the proposed modification of the spent fuel pool at the Commonwealth Edisc:n Station at Zion, Illinois. This testimony pertains to contentions 2 (e), 2(h), 2 (j),
2(f) and 4(a) as described in the Board's order I'ollowing Pre? ' ring Conference, January 19, 1979, and will demonstrate that the prc, sed modification application does not deal with numerous unresolved technical problems and that many essential procedures are yet to be developed by the Applicant. The testimony will first address those contentions which have not resolved problems of cerrosion and degradati:
of the Boaral: 2(e), 2(h) and 2 ( j ). Accident scenarios and ef fects,
including sabotage, will be addressed in the testimony on 2(f) and Board questien 4(a).
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TESTIMONY OF GREGORY C.
MINOR concerning contentions 2 (e),
2(f), 2 (h), 2 (;) and 4(a).
My name is Gregory C. Minor and I am a partner in ME3 Technical Associates in San Jose, California. I have had nineteen (19) years experience in the nuclear industry, including design, main-tenance and checkout of nuclear reactor systems, design and testing of safety and control systems for use in nuclear reactors, and the perform-ance of safety analyses for various local, state and national organizatic A statement of my background and qualifications is attached to this testimony as attac5 ment I.
The following testimony concerns the proposed modification of the spent fuel pool at the Commonwealth Edison Station
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- Zion, Illinois. This testimony pertains to contentions 2 (e), 2 (h), 2(j),
2 (f) and 4 (a) as described j n the Board's Order Following Prehearing Conference, January 19, 1979, and wiil demonstrate that the proposed modification application does not deal with numerous unresolved technical prcblems and that many essential procedures are yet to be developed by the Applicant. The testimony will first address those contentions which have not resolved prob.' tms of corrosion and degradatic.
o f th : Boaral: 2(e), 2(h) and 2(j). Acc:.ent scenarios and effects, including sabotage, will be addressed in the testi=ony on 2(f) and Board cuestica 4(a).
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u-2 (e) The amendment request and supporting documentation do not adequately discuss monitoring procedures.
In the light of the proposed modification and long term storace of nuclear spent fuel the applicant should clarify the following:
(3) Me thods for detecting the loss of neutron absorber material and/or swelling of stainless steel tubes in storage racks.
(4) Details of a corrosion test program to monitor periormance of materials used in construction of the racks.
DISCULSION
- 1. The Applicant has described a general plan for verifying the presence and adequacy of the neutron absorber by QA inspections during.conctruction, by conducting neutron absorption tests after installationl, and by a coupon test during the life of the pool 2, However, the details of how this plan will be carried out are not clear at this time. Nuclear Regulatory Commission Criteria fo r overseeing surveillance are also not clearly developed 3, T.:e procedures to be utilized by the Cc==cnwealth Edison staf f for reviewing the racks, for installing the racks or for inspecting the racks in the Zion pool have yet to be written 4 It is therefore ICICO respcnse to NRC Second Round of Questions 1/24/79 page 4.1
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' Deposition of _rr ank Al=e te r, May 19, 1979, page 47.
4 Sepcsiti:n of Walter Shewski, May 19, 1979, pages 22-24 51/
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impos sible for the ::RC staf f co properly evaluate the surveillance and inspection programs whi :h have been proposed.
A plan has been described to test the tubes prior to placement of spent fuel. A neutron source will be inserted into each tube and measured with sensors to determine the neutron attenuatun of the tube and the Boral. There appears to be no plan to measure the condition of the absorbing =aterials in the racks after spent fuel has been placed in the cells.5 Visual inspection would be unsatisfactory for all but the cells on the edge racks next to the walls.
The plan for In-service Inspection (ISI) is to suspend a number of Scral and stainless steel sample vented coupons in the pool as an indicators of the degradation of the materials used in constructing the borals racks. Periodically, some of these coupons will be removed and tested. The test will involve only a few samples and may be misleading unless the sa=ples expe rience the worst-case corrosion environment in the racb. Presently, che Applicant has not defined the specific criteria by which it will evaluate the coupon tests.
In 1979 swelling in Boral racks was detected in the spent fuel pools at Mencicello and 3rcwn's Ferry Unit No.
- 3. The swollen racks utilized a sealed cell designed by General Electric Company.
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e cIluate the surveillan:e and inspection programs which nave been prcposed.
A plan has been described to tes: the tubes prior to placement of spent fuel. A neutron source will ' e inserted into c
each tube and measured with sensors to deternine the neutron attenuation of the tube and the Scral. There uppears to bc no plan to mesure the condition of the absorbing materials in the racks after spent fuel has been placed in the cella.
Visual inspecticn would be unsatisfactory for all but ene cells on the dge racks next to the walls.
The plan for In-service Inspection (ISI) is to suspend a number of Boral and stainless steel sample vented coupons in the pool as an indicators of the degradation of the niaterials used in constructing the borals racks. Periodically, some of t.hese couponc will be removed and tested. The test will involve only a few satnples and may be misleading unless the sa=ples e:cerience the worst-case corrosion env:.ronment in the racks. P re s en tly, the Applicant has not defined the specific criteria by which it will evaluate the coupon tests.
In 1973 swelling in Boral racks was detected in the spent fuel pools at Menticello and 3rown'c Ferrf Ini Sc.
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The swollen racks utilized a sealed cell designed by Gencral Electric Ccmpany.
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Leaks in the welds allowed water to enter the cells and
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f acilitate corrosien of ~ the aluminum plates of the Scral. Hydrogen gas generated by the corrosion caused bulging af the thin shroud on the cell. To resolve the problem vents were drilled on the top of each swollen cell in order to release the trapped gas and reduce the swelling.
Commonwealth Edison, aware of these incidents, has decided to prevent this known cause of swelling by starting with a vented design for the Zicn racks. The penalty for this decision is the f act that some corrosion will occur in all cells over the life of the plant.
Brooks & Perkins report No. 573, dated July 7, 1978 is cited as the justification for venting the cells of the Zion dense storage racks 6 This report cites the general corrosion of aluminum as 0.16 mils per year (or 6 mils over a 40 year period) ; galvanic corrosion rates of 0.1 mils / year (4 mils over 40 years); pitting depths of up to 5 mils in only 1/3 year and the generation of substantial gas pressure due to radiolytic decomposition of borated water in a Boral matrix exposed to a high neutron flux for a short ti=e. Each of these conditions is marginally acceptable for the 10 mil Aluminum clad under the proposed pool environment but they leave' no
=argin for possible ccmbined ef fects, unknowns and uncertainty.
Cc==cnwealth Edison evidence involves research and tests of only 1-2 year perieds and there has been no experience with vented cells over a 42 year lifetime.
- 'CICC response 20 NEC seccnd round of ques cns 1/24/79 page 2.1 3i/
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Leaks in the welds alicwed water cc enter the cells and f a cilitate corrcsion of the ale =inum plates of the Boral. Hydrogen gas generated by the corrosion caused bulging cf the thin shroud on the cell. To resolve the problem vents were drilled on the top of each swollen cell in order to release the trapped gas and reduce the swelling.
Commonwealth Edison, aware of these incidents, has decided to prevent this known cause of swelling by starting with a vented design for the Zicn racks. The penalty for this decision is the f act that sene corrosien will occur in all cells over the life of the plant.
Brooks & Perkins report No. 5 73, dated July 7, 1978 is cited as the justification for venting the cells of the Zion dense storage racks 6 This report cites the general corrosion of aluminum as 0.16 =ils per year (or 6 mils over a 40 year period) ; galvanic corrosion rates of 0.1 mils / year (4 mils over 40 years ) ; pitting depths of up to 5 mils in only 1/3 year and the generation of substantial gas pressure due to radiolytic deccmposition cf borated water in a Boral matrix exposed to a high neutron flux fer a short time. Each of these condi" ions is narginally acceptable for the 10 mil Alu=inum clad under the f. cposed pool environ =ent but they leave'no
=argin for possible ccmbined effects, unknowns and uncertainty.
Cc==cnwealth Ediscn evidence involves research and tests of cnly 1-2 year pericds and there has been no experience with vented cells over a 40 year ' fetime.
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Note,ncne of the conditions lis ted in the Brocks and Perkins report would be expected to occur in a non-vented tube or cell, provided that a water tight seal. auld be maintained over the projected 40 year life of the racks.
STATrMrNT OT COS""B"rIONS 2 (h) The amendment request and supporting docu=entation have not analyzed the long term (including storage during the operating lifeti=e of the reactor) electrolytic corrosion ef fects of using dissimilar allofs for the pool liners, pipes, storage racks and storage rack bases, such as the galvanic corrosion between unanodized aluminum as is used in 3rcoks and Cerkins storage racks, and One stainless steel pool liner.
2 (j ) The amendment request and supporting documentation do not give sufficient data to fully assess the durability and performance of the Boral-stainless stell tubes which form the spent fuel storage racks.
(1) there is inadequate analysis of the corrosion rate of the tubes.
(2) there is no calculation of the ef fect of water chemistry on the Boral within the stainless steel.
(3) there is no cention of the possible swelling of Boral within the stainles s steel tubes, a condition which could affect, among other things, removal of fuel assemblies from the racks.
DISCUSSION There has been very little actual operating experience with scral/ stainless steel racks in a dense s:crage pool configuration.
The effe::s cf using ventef 3cral racks are even less known. It is generail agreed tha: if pool water is all:wed Oc enter the tubes electreif ic cerrosion will cccur ce: ween the alaminum cladding CJf/-
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on the 3cral and the stainless steel shroud. Thus the decisien to vent, insures that water will enter rack tubes and will.:errit electrolytic corrosion. The icng term ef fect of this corrosion is not certain. So far, tests that have been done are sher: term tests en a small nu=ber of sa=ples. The results of these tests,
which are nominally one year long, are being extrapolated to 40 years in order to attempt to determine the impact over the lifetime of the racks.
Brocks and Perkins and Leckenby, the fabricators cf the Boral and racks which are to be used at Zion are also naruf acturing racks for dense storage of spent fuel at the Salem reactor also in New Jersey. Ecwever, at Salem a decision was made to seal the tubes (a non-vented design) because of the uncertainty of possible long term ef fects of corrosion in a vented tube. One of the Exxon researchers stated the reasons for utilizing the sealed tube as follcws:
"...one you have vented every storage cell its too late, you can never go backwards and that 's '
what you're looking at. Ycu don't know the con-sequences of 30 or 40 year Boral performance in a specific pool environment. If you have any storage cell vented, you don't go backwards. The consequences of that if something unexpected should happen, in our judgnent, is much more severe than the nuisance factor of a randem--which we don't expect--havin9 to vent a fuel assembly, a storage cell with a fuel asse:bly in it. ",'
, Testincny of Themas Eckhardt, spokesman for Exxcn, desi ner of the Sal =r 7
racks In the =- =- ^' Oublic Service E & G Co. ( S ale.T. 5:aticn, ~Jni:
No. 1), Docke: No. 30-2 2,
Hearings before the ASL3.May 4, 1979, Sale-
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cn the Scral and the stainless steel shroud. Thus the decision to vent, insures that water will enter rack tubes and will permir electrolytic corresion. The long term ef fect of this corrosion is not certain. So far, tests that have been done are short tern tests on a small number of samples. The results of these tests,
which are nominally one year long, are being extrapolated to 40 years in order to attempt to determine the impact over the lifetime of the racks.
Brooks and Perkins and Leckenby, the f abricators of the Boral and racks which are to be used at Zion are also manufacturing racks for dense storage of spent fuel at the Salem reactor also in New Jersey. However, at Salem a decision was made to seal the tubes (a non-vented design) because of the uncertainty of possible long term effects of corrosion in a vented tube. One of the Exxen researchers stated the reasons for utilizing the sealed tube as follows:
"...one you have vented every storage cell its teu late, you can never go backwards and that 's '
what you're looking at. You don ' t know the con-sequences of 30 or 40 year Boral performance in a specific pool environment. If you have any storage cell vented, you don' t go backwards. The consequences o f that if something unexpected should happen, in our judgment, is much more severe thtn the nuisance factor of a random--which we don't expect--having to vent a fuel assembly, a storage cell with a fuel assembly in it. " '
Testi=cny of Thcmas Eckhardt, spokesman for Exxon, designer of the Saler racks In the Matter of Public Service Z & G Co.
(Salem Staticn, Uni:
No. 1), Occket No. 50-272, nearings before the ASLE May 4, 1979, Sale.T
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The structural strength of the Scral plate is derived frca the binder and the 10 mil Aluminum cladding. There are two possible failure acdes of these plates th a t have not been addressed and warrant further attention - particularly in a vented cell. One is the gradual delamination of the clad due to a weak bond during manufacturing. The second is the corrosion of the binder af ter pitting or leakage has worked its way through the 0.010 inch clad. Borated water in this region under the influence of a neutron fl.ux has been analyced to cause slew gas build-up due to radiolysis of the water.8 In his affidavit, previously submitted 9, M.r. Frank Almeter identified corrosion rates of such a magnitude that if pref ected ever the 40 year pool life, the entire 0.010 inch thickness of the clad could be corroded. If that were to occur it could expose areas of the Boral matrix of B C and its aluminum binder. This would allow 4
corrosion to occur on the binder itself and threaten the integrity cf the Scral plate. M.r. Alreter is now referring to early 1950's 10 research which gives lower values for corrosion, but ::ay not be as applicable to Boral as the later tests cited in the affidavit (Exxcn and North Carolina-Virginias).
a "Erccks and Perkins Reports 572-IXPERIMZ:!TAL OBSER7ATION O.7 SORAL PLATES I:CASIO IN STAI:ILISS STII;
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,~1rticle by D?aLEY, 1956; see Alrecer depcsitica 5/13/79, page IE.
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Anodizing the Aluminum surface in the Scral plate would reduce the amount and rate of corrosion of the surf ace. However, this alternative design approach has not been addressed in the application on supporting documents.
STATEMENT OF CONTENTICN 2 (f) (1) There is insufficient documentation to establish the methods by which the Applicant will positively prevent the movement of heavy objects, such as shipping casks or empty fuel racks, over the pool during modification; thus accidental droppings of such heavy objects, which could lead to unacceptable damage to spent fuel or the pool liner and cmsequent release of radio-nuclides, has not been precluded.
(f) (2) There is insufficient information regarding the me*. hod by which accidental dariage to stored fuel assemblies will be prevemted during the installz. tion of the new poisoned spent fuel storage racks.
DISCUSSION Normal pool operating procedures restrict noving heavy chjects over the scent fuel pool. Duri ng the rack modification it will be necessary to move the new racks (the larger ones estimated to weigh over 15 tons) over the pool using the largest bridge crane.
Sis will require defeating the nor=al interlocaks. Since there is spent fuel in the pool (about 350 fuel bundles) the movement of the heavy racks ever de pcci could result in damage to the fuel if a rack is dropped. Although it is a low probability event, nenetheless it deserves at least a review. This has not been analyzed in the SEE cr Application.
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Anodizing the Aluminum surface in the Boral plate would reduce the amount and rate of corrosion of the surf ace. However, this alternative design approach has not been addressed in the application on supporting documents.
STATEMENT OF CONTENTION 2 (f) (1) There is insufficient documentation to establish the methods by which the Applicant will positively prevent the movement of heavy objects, such as shipping cacks or empty fuel racks, over the pcol during modification; thus accidental droppings of such heavy objects, which could lead to unacceptable damage to spent fuel or the pool liner and consequent release of radio-nuclides, has not been precluded.
(f)(2) There is insufficient informati.
regarding the s
methods by which accidental dcmage to stored fuel assemblies will be prevented during the installation of the new poisoned spent fuel storage racks.
DISCUSSION Normal poci operating procedures restrict moving heavy objects over the soent fuel pool. During the rack modification it will be necessary to move the new racks (the larger ones estimated to weigh over 15 tons) over the pool using the largest bridge crane.
This will require defeat 1.;g the normal interlocaks. Since there is spent fuel in the pool (about 350 fuel bundles) the movement of the heavy racks over the pool could result in damage to the fuel if a rack is dropped. Although it is a low probability event, none theles s it de se rve s at least a review. This has not been analyzed in che SIR cr Application.
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STATEME' T OF SOARD CUESTICN 4 (a) (3) The Licensing Board propounds the following questions to each of the parties, with the request that evidentiary showings on each of the questions be made at the forthcoming public hearing in this case :
(a) Will the proposed modifications of the spent fuel pool and/or the operation of the Zion station with increased spent fuel pool storage capacity:
(3) increase the potential risk of industrial sabotage to the Station or to the special nuclear material?
DISCUSSION The risk due to sabotage may be treated as the product of the probability of sabotage and the consequences of a successful sabotage attempt (Wash 1400 definition of risk).
The applicants documentation provided with the applicatior has not shown an increase in security or sabotage prevention over that utiliced in the previous pool rack configuration. Security doccments were not made available to the intervenors during discovery therefore it is not possible to constructively ccament on changes to the plan which might be made necessary by the proposed modification. It should be borne in mind, hcwever, that the modification has already attracted a great deal of public concern. Demonstrations have been held at the ion Station as recently as May 12, 1979, to protest the licensing cf additional spent fuel storage. If such attention continues sabotage may beccme a more likely event. The additic. al x=ounts of radicactive material to be stored in the spent fuel pcol will make the ef fect of an, successful sabotage incifent involving the pocl that much mere J l, pads )(-c,ver 1
2000 hacardous. The new racks will centain over 10 corp 3 cuJ c
bundles) spent reacters fuels from "'icn units 1 & 2; some =ay be extra high burnup fuel as a result of planned experiments. The pool will therefore contain al= cst 3 times the inventory of the high level wastes and the actinides with longer half lives, but not an appreciably larger quantity of short-lived gases and fission by-products.
Assuming that the probability for sabc tage succeeding in releasing the radicactive by products contained within che spent fuel remains the same as previously analyzed, (e. g.
ISAR) the amount of radiation which could possibly be released is considerably greater.
In the event that a greater quantity of radioactivity is releasec. to the environment through a sabotage event, the potential consequences and, therefore, the risks are increased.
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bundles) spent reactors fuels frcm Zion units 1 & 2; scoe =ay be extra high burnup fuel as a result of plar.ned experiments. The pool will therefore cor.tain al=cs t 3 times the inventory of the high level was tes and the actinides with longer half lives, but not an appreciably larger quantity of short-lived gases and fission by-products.
Assuming that the probability for sabotage succeeding in relecsing the radioactive by products contained within the spent fuel rer.tains the same as previously analyzed, (e.g. FSA?) tne amount of radiation which could possibly be released is considerably greater.
In the event that a greater quantity of radioactivity is released to the environment through a sabotage event, the potential consequences and, therefore, the risks are increased.
517 207 la
I have prepared and read the foregoing testimony and swear that it is true and accurate to the best of my knowledge.
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Minor Subscribed and sworn to before
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517 oc}0'
_ e _
U'iITED STATES OF AMERICA NUC' EAR REGl'LATORY COMMISSION BEFORE THE ATCMIC TETY AND LICENSING BOARD In the Matter of
)
)
CCMMONWFJJ.TH EDISON COMPANY
)
Docket Nos. 50-295
(" ion Station Units 1 & 2)
)
50-304 CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing TESTIMONY on behalf of the State of Illinois dated May 29, 1979 in the above-captioned matter have been served upon the following by deposit, first class, in the United States Mail, this 29 th day of May, 1979.
Edward Luton, Chairman Atomic Safety & uicensing Board Atomic Safety & Licensing Board Panel Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commi-Washington, D.C.
20555 ssion Washington, D.C.
20555 Dr. Linda W.
Little Research Triangle Institute Atomic Safety & Licensing Appea P.O. Box 12194 Board Panel Research Triangle Park, N. Carolina 27709 U.S.
Nuclear Regulatory Commis s Washington, D.C.
20555 Dr. Forrest J.
Remick 305 E.
Eamilton Avenue Docketing & Service Section State College, Pennsylvania 16801 U.S. Nuclear Regulatory Commist Washington, D.C.
20555 Michael Miller, Esq.
Philip P.
Steptoe, Esq.
Richard Goddard, Esq.
Isham, Lincoln & Seale Steven Goldberg, Esq.
Cne First National Plaza Office of the Executive Legal Chicago, Illinois 60690 Director U.S.
Nuclear Regulatory Ccmmiss Mr. Rick Ronter Washingron, D.C.
20555 617 Piper Lane Lake Villa, Illincis 60046
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SUSA2. N.
SEKULER
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217