ML19224D200

Submits Addl Contentions Per ALAB-535,issued 790411

ML19224D200
Person / Time
Site:	Allens Creek File:Houston Lighting and Power Company icon.png
Issue date:	05/25/1979
From:	Doherty J DOHERTY, J.F.
To:
References
NUDOCS 7907110073
Download: ML19224D200 (18)

Text

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g% I ' ' / c In the Matter of:

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cense proceedings subnits the following contentions in response to the Board's Order of April 11, 1979. Intervenor was grantMCAL PDR until May 25, 1979 to subnit contentions by a succeedir.g Bo u d Order. These contentions were not subnitted previously because the"s either had nothinc to do with ch'inge in "elant design or -

were not based on entirely new evidence. Cone arose due to events during the period granted by the Board to subnit con-tentions.

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tha resolution ofk the A?tlS ceneric issue can be in-

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_2-e en-,2 v v a a. .r.n-a 10 As of May 23, '979, there wore eight (3) contentions of this Intervenor either acce'ted or in controversy. Hence num-bering of contentions begins with "9".

9. Intervenor contends Applicant'.s safecy systems contain many non oa#a"sc - v -- d c . o_~ e e u _d c. ". e m "e 4"mo.

r m._o k _4 - 4_ o m u e 1. o- " * 'd n .oe a " Board :To ificationP 37 the Cffice of liuclear >.eactor Regu-lation. Applicant's Table 3.10-1 of the F5A2 shows a large number of conponents which are qualified under 12EE-323 and 1EEE~344 but not under 1EEE-279 7articularly significant to transient nitir,ation are level switches, pressure switches, oressure indicators, radiation monitors, trip units, electro _ic modules for control rod drive units, valve motor operators, tecperature switches, indicators and elements, recirculatior.

valves, and actors. Intervenor contends the use of these coa-conents,,of below safety grade viol.ates General Design Cri-terd.a (GDC) #29, and 10 CFR 55a(h) and entails risk to his health and safety interests. Intervenor recuest that the Board enforce GDS #29 and 10 CFR 55aCh) on the equipment listed here and in rable 3 10-1, and equipment not listed that is used to citigate transients.

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.mu- n - a-- - es a ==- ..o *v sufficiently crotected because applicants diesel aenerator s.vs-ten to the Eigh Pressure Core Spray (HFC3) and to the rest of the nuclear plant is unreliabie in start up and operation.

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that accordin to "UREG-0660 (Feb. 1979) produced 122 start-up

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i.e. fuel oil stored with lubricating oil and used as a lub-ricant (Brunswick, Unit-?, Octo'er c '975) and outside storare of diesel gener2:or's prior to plant start-up, resultin~ in water logging (Ft. St. 7 rain, June, ^975).

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. -- - unCS '"d a "k4."A -- - . ' u' " "vb e balance of the plant systens, (b) a higher standard than 93 starts per 100 be used in requiring additional infornation to the NRC, (General Electric Technical Specification c . S .1.1. 4 for BNRs) and that (c) Surveillance Ecuirenent a.5.'.1, should recuire an every 3 day surveillance, and all other surveillance tines halved in view of the serious consecuences of cower failure to a nuclear plant.

11. Intervenor contends that danger of a spent fuel pool less of coolant accident (LOCA) are not fully acccunted for in Appli-cants plan to store large amounts of spent fuel r;f.s in the spent fuel pools both in the containnent building and the rad-waste building. There is danger of spent fuel pool heat-up and evaporation or evaporation induced criticality event if all personnel cust leave the AC:iGS because of a serious acci-dent at a nearby nuclear plant ("AC"GS Unit-2") or due to a nore serious accident at South Texas Pro.iect_ Unit 1 c-a 2 or n , i; a. "41.1s U-4". ' 'm .d o . T. .e m, 1 1 ,,a- -oc o . - a l- -ue'- 1. = a < a , "ka

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reccror can be shut-down, but the scent fuel pools zould be decer. dant on pernanent replenishnent of water fron coolant m.a .o- c-e_V.~~g

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accident (LCCA) thermal shielding and insulacion may 'ce ripped off or otherwise released or serarated from in-containment cuil-a4 _ _- _., ,4-4..3."k._

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failure in the core of ACMG3. That "SLEM cannot datect

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systen at- Dresden Unit-3 in October of 1973 inere an esti-nated 200 fuel rods fail"d during an operation _1 transient and at Three Mile Island Unit-2, where fuel failure was not detected until 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the feedwater transient of March 28th. The HSLEM cannoc be set low encuch to detect racii fuel failure with sufficient sensitivity due to the presence or J, a w.nica ,

gives .,alse positive 2,1arns un,ess the nonitor-is set too high to detect ranid fuel f ailure.

NUR2G-0401 (March 1973) concludes that a BhR flo'.t blo c'.: age accident resultin in fuel failure cannot be detected with certainty by the MSLRM. This intervenor argues:

(a) Since the M3LEM does function without U 6 interference in a Pressurized Water Reactor (PWR) that nuclear stean suc.ol.v . systen should be constructed at ACNG3, or

(b) Applicant should consider the use of a Ganna Dose 7.at e Alar =, enploying an Ionization Chanber (See: Health .hvcica, 3-, 7.w...,10,0, o g o- 5_gg T, .

The higher power core density a n d hi6h total output thermal power of AC5G3, nake rapid fuel failure a hicher c probabilit-.

than any Other functioning MTR, and thus the contention is

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16. Intervenor conte:. 's durinc Ant cicate: Transient without SCRAM '

(A LS), Fower Coolant Mistatch Accident (FCMA), delayed SCR.E or other transient causing events, the fuel rods will cause steam blanketin of the Z ergency Core Cooling Systen (ICCS) coolant, preventing them fron being adecuately cooled, leading to fuel melt with cons ecuent explosion danger from a molten metal-water. reaction or inability of the reactor to cool a o.ile of fuel which has nelted and fallen to the botta= of the reactor vessel. Further, a prinary research objective of the Loss of Fluide Test (LOFT) facility appears ('iUR2G-0006, March, 1979) to be to understand heat transfot' :uc .- s this during a cooling e=ergency, e.ven though the major tests on adequacy of ECCS used depressurized fael rods. Interve or concludes his health and safety interest may be impaired by stean blan-

'ceting of the fuel rods and that this roactor with its extremely hi-h o power core densit.~ and high thernal output =akes the prob-les a particularly great ha ard.

17. Intervenor contends pressure from blowdcan follo. ting a cower ex-cursion acaideat (PZA), Loss of Coolant Accident (LCC1.) or iower Co'.l=m 'v M.i su e ~" -" 3.c _i d '. n"v ( O_ 'v*. m' ) ^ ^ ^ 4_ . a.

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.n o.1. .= 3 .** a .= -q r* -.,a.,

a+

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,x deterioration with use or age in reliability. This Intervenor c^".a_d~e .i. p gl . i ---" _" ", n, u o"o p o.4da. r a. ' ". a .' "r.l.^a o

a = d. a " ;" .= =. v c . a .1 c,: _~_m.-, - 4 . m_, .; - v.o m . o _2 .m. - o ,. _ o m-

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.- ,b,& 4.. ,n of clowdown pressure "c the suppr'ssica pool.

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not be tri. coed rapidlv. . In-core pressure sensors which are "a.liad u'fv-

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m "m _ - ." 4. - i m e , ' 3, "< 5- . ' ' , . "

22 EWRs, Nuclear Safetv, 19(1) P. 82, shows 128 occureccas, and su:: arising 1977, the saae journal (20(1), p.84) shows 125 occurence reports for 23 3WZs. This journal rhows 246 reportable occurences for valves in 1976 and 241 for 1977. The high level o# ra o. r"e v- b .- l a ...- u

^

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. om. , w 4 m. __ w m power core density proposed for the ACHG3 3NR/6 reactor the unreliability of the recirculation punot trio. systen is a .

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perience of o-her licensees to deter ine which nanufacturer's

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.. m m.mo us- T. ..v . .s.. -.. .., ., ,., , , ,vas ,. . .d o- ,,7,4,--- -u v m_ , o u, , a be required to ' resent evidence the systea nroposed is surerior u

o w

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p. 4

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eters of AC'IGS.

20. Fuel perforcance caleclations using GZGAF-III ,lus fission gas wu-mu,s m uw,-

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v o .-m ..e . 4 o n r m ,., ., o o , .co . y --m_a._m.,

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per ton of u~,.nium, have only been determinei by Applicant's vendor to bound the 3'iR /3 systen with recard to thc only effec-ted- s e f a_ "o ", o" ,vo" "o.. = ~ , "oha

.- aa " c m'. - mm y- ^oro v - -^oo'i'r v .c a' s stea (7"^o^).

vv J. i "e "- a c". 3. /6 , T "v = "v =" o *. ".. "m"v n "..A-o" - o_e 4 n' .#.4 a a..*o 'lv a _', ion o# "v S e 2"CA-vo or use of a n"'.n'Q.,/5 =ay be required because the maximum tennerature, ',321 F., re.:hed in the calculation with a B'JR/S, is but 379 F. short of the LCCA limit, The B'.iR/6 design is unte sted.

.i n oo _-,. m_ - o . cm.. . e 4o- -v w..o. .# ,70/c- -

4- u, n.- o ,-s a - .ov, . use e wv_,c ,,u,-c o. app, .

. 4-can-'s vendor has not determined if these calculations clearlv, apoly to a 3'JR/6, and that these should be accomplished before the operating licese hearing cta special hearing or at the con-s + . L, e 4 v .,e n 1.4ceuve yoa. i m o . .uu . -._+.u, ,

_-umo,a, a.- uuo e - ,n_ eo,u l uooe l a- ; ,.m, u v o.

large measures need to be taken, then a 3'.!R/5 should r= place the I

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economic interest would be ef ected. Although deneral Electric has issued its taoical report, the Staff's consultant cuestions the results, so Intervenor's contention has a basis.

22. Intervenor contends the control rods na7 develope cracking in the blad.es in-core which hold the neutron absorbing baron carbide, B4C. Since the centermost rods are suoject to the greatest neu-tron absorbing recuirement, these may crack severally, resulting in an amount of B4 C greater than the highest rod worth being dis-persed in the coolant and resulting in inability to shutdown.

Intervenor allges an economic interest because prolonged inade-quate shutdown will cause loss of use of the plant, and likely strain Apnlicant's system ahich is not interconnected with any utility sending power out of the state. Further, the use of the 8 x 8 (sinus one) fuel assembly makes the issue relevant to ACNGS because the control rods each have to absorb more neutrons than with a 7 x 7 fuel assembly.

23. The design based loss of coolant accident (LCCA) assuces a large pipe break due to a fault in the pipe while the reactor is oper-ating at full power. However, the accident could also occur by being initiated by the pressure surse due to an overheating transient such as a power encursion or coolant flow blockage.

Intervenor contends his health and safety interests are not pro-tected by the design based LCCA, because of the accident possi-bility cited and that the Energency Core Coolin.g Systen (Z:03) should be designed to citigate such an accident. Applicant's large a:wer core density makes consideration of this proble-at the construction license stage appropriate.

24. The desir. 52:e' :: rol roi d.rc e cc:ident titi 1:icn ices :t

'rotect In 3r 2n:r's health, saf't7 2nd 2:;nanic interest - M --

fici'n:17 :ecause no re r:1' :-2ctivit- chan :21:ul .tei ,_11 :e released and acre d:nn e will ce d:ne to the roan r b~ Y e reactivit7 inicircei ':n this design baced acciient. Recen:1 ,

E C- ': 3527, "2:1 Jrop inalysis _'o r :'.53 " , ch:.tei 712: : .'_ e 23' cal:rica mer :r :.: ae f: :nsrr field li.:it i _f ce e:::eeded 33l ()h kbh ) h -(3]Y l llT Mn M Mfl$j[ h

-s 4 .' " N.e .- a. _,a " 4

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. .s 1 - o d ". ' "v ".. e have no t been changed in 3'.TR re2ct.'r.,, such that the 1.N5 can be exceeded in "h. decirn based accident as is shown in the u.

i g .,.u- ., , u . 4. _i m_m. , 2.1, v , _m.: i. .

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Intervenor contends the control rod s stem must have a greater number of rods with each controllig a scaller nuater of fuel rods in order to bring the reactivity worth of each rod to no more than 1.N5 and the peak energsv -ield to less than 250 cal. per gram of fuel.

25. The design based accident for a flow blockare inciden; is in-adequate because it assures blockage of but one fuel assembly.

The only knc.n accident of this type (a very serious one) in-volved blockage of two fuel assemblies (Ferci, Unit-1, 1966).

In addition, ITUREG-0401, " Fuel Failure Detection in Operating Reactors," March 1973, _; age 23, concludes that, ". . . a possi-ble excection (to adequacy of fuel failure detection) is asso-ciated with a postulated 3'lR flow blockage accic'ent which night proceed undetected in its early stages." In-core and in-reac-tor c;tlerial; and parts nay work loose J.ue to corrocion or

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box cortions. Stean dryer section could do this also. 'cihere

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design based accident and incorperate any new developments thich incrove flow blockage detection re orted to be in"ex-perimental stages" in UURZG-0401.

26. Zhe reacto: "ctud bolts" any Jin c ac;- leading to a severe accident. Apolicant has stated in the PSAR that since the coderating unter is unboarated, the bolts do not need inspec-tion or oth9r safe:7 procedures. Intervenor contends bolts should be visually inspected at refueling time because the consecuences of containaant vessel head partial li.!t-off or other failure presents a high risk to his safety because the reactor vessel fi'aion products would be releaced into the containment building where they would be difficult to cool. If the head blew off, and pierced containment building roof, then otvioucly this would be vorsE. '! hare the proposed ACNGS will have such a high thernal powcr output, the accident liklihood is greater than other B'dRs.

27. Intervenor contends that the pedestal concrete c' ACNGS may be weakened by the heat from a power excursion accident (PEA) or loss of coolan't accident-(LOCA) such nat restart and coeration of tTe reactor tould endanger Intervenor's health and safety through subsequent reactor novecent due to the original thermal dacage to_tho. pedestal. Subsecuent damage would include but not be licited to pipe breaks and other accidents costing auch to recair and releasing radio-activity in encess of 10 CFR 50, Ap?endin 1. Damase occured to the Dresden Units II and III, 4_

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m um *b ee General Electric Zngineers testified at Senate Ecarings in 19~5, and a small reactor tore loose frc its pedestal in T. a. n- m a 4.- - a, c q wa (cr qT .c , , , , y. 4. .,. - , ,s s y. o. ,. m. . v- m - vc a v, .. , r s~

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venor contenis the proposed .433S scou'1 be constructed to

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n a ,c. u, 4_ soc a,ceo, m -_ n . p=an.ac _,,. m in vi3w of 7he orobable incessibility to evaluate Three Mile I s lm.nd , Unit-2 for a considerable tine, snd ApTlicant should file such clans for Staff evalua; ion before the construction license hearings. to o.rotect o.ublic safety and avoid expensive retrofit. Since ACHGS is far nore thernally rowerful than the reactors that have been subject to pedestal danage the aparaorzate forun is these hearings.

23. Apolicant's PSAR does not consider the possibili:: of a control rod e.s action accident adequately. This endangers intervenor's interests with a reactivity insertion accident J.pplicant states ( P. 15 1-75 of the PS!.R) that, "In all cases the sub-sequent withdra.tal speeds (that is speeds due to an ' unplanned withdrawal' uhich are variable) are less than a rod drop accidnnt",

infering the consequencas nust be less. Sut, in a control rod ejectica, the rod would be forced out by the containnent pres-sure and possibly the pressure in the SCRAM discharge volune tank (SD7T) would be ."dditi onal, craating a nore ranid rod Thc; such SDVT cressures h2ve eJ'ection as oc.o.csed to rod dron. . .

occured is set forth in TerFIRG's contention ;;32 of .'.ay '6,

^979. xnpil pulling of a rod, le?. to a fatal oower ex:ursion

ith the Stationcrv Low 'Jower Plant (S-L-1) renctor in J anucrv v 1

'961. Apalicant should be required to show its control rod c,co u es

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e a.' a.*~a" y --- econom.i- i.n". e -a s *- e are inperiled because J.pplicant refuses. to inter'onnect with any .

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this cannot be shown, Appliennt aill be recuirad to inter-connect with out-of-state intercoanected ".tilities before a construction license is granted. Or, alternatively Apolicant u s.. . u, .

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(a) shut down ACNGS when there are-severe climactic con-ditions; or:

(b) n.rovide a third ~enerator Jnd cenerator start-un. then - -

severe climactitconditions occur.

31. Intervenor contends coolant flow induced vibration of the fuel assenblies vill lead to degraiation of the Local Power Range Monit.rs (LP2Ms) signal due to wear or other danage, to the extent reactivit7 monitorins and control in several significant fuel rods will become unreliable, exceedin~ tne

_+ 5.M4 error in Radiation Monitorin6 Svstens and leading to -

aininistrative derating of the reactor. Intervenor contends Applicant should provide additional LPRMs to give additional information on the BWR core's power characteristics cufficient to prevent either adninistrative derating or accident hacards such as power excursions. Current plans for 3 LPRMs are not sufficient.

32. Intervet.or contends the vaporization rate of the Energency Core Cooling Systen (2003) water during a design based 1:ss of cool-ant accident (LOC 1.) is nore rapid than the General Electric (GI) nodel predicted for an 8 x 5 fuel assembly coro such as .s 1CUGS. This w2s reported by the 1.dvisory Connittee on Reactor ;_;

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venor contends:

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to; much on reactivity and pwer excursien control by the Poppler effect. .'tpplicant's reactor nanufacturer, General Electric (GE) u c o ,a. co

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o - u, +m n,o c e c ,m e +. u, , .4 v - .e -__ ,,,, 1- ~e u_ a_tan .oo instead of uranium oxide fuel. Metalic uranium fuel pives up its fission heat =uch more rapidly than oxide Z'M such that the coolant heating effect (Doppler ef'ect) which would reduce the moderating ability of the coolant and decrease fissioning is less in the ACGGS case than the experiments in which the extent of the Doppler effect in mitigation of reactivity initi-ated accidents or transients was determined (3ORJ.I -1). Oxide fuel tests such as 5?Z2T-1 had waterloc_ qed fuel rods > which diminished their reactivity, and 3 FEET-3, was never tested for upper limit of Dop;ler negative reactivity effect, and the current Power E"--t Test Facility (PETF) usas depressurised fuel rods which di2inis'nes reactivity when inserted. Inter-venor contends there is no exp'ricental datn to show the Dop?ler effect will function to protect Intervenor's health interests against a severe explosion as cuch as G2 and Appli-cant believe. Further, ACNG3 is the largest B'fR proposed and hence the effect of overesticate of Doppler reactivity .

feedback will be more severe and core likelv than with an7 .

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. "..n.- a. a. 't "..le _Tom- l a nd U". 4 ". P 4. . ^ id a. ."."v . , o u'o-stantially before (35 years) the licensing period of ACITG3 will be comple.e (the year 2027). Intervenor will be farther eco-ncaically injured if the proposed USSS is installed because obtaining (1) Pnrts, (2) infor ation, and (3) cualified repair and advisory personnel fro: GE will be acre difficult as years progress. Such " difficulty" vill be experienced as delay, -

plant outage, UZO ordered der tings, nnd operating under less safe conditions. As there are few (if 1ny) E!R-6 / Mark-III uaits in operation or preparation, these three itens Cay also be inp ssible to obtain wit'raut grea; expense and be of poor o,u..' i"o g 4" . GP a "..i k' aws. 'ac_uoe v^f *ka

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(a) A different UES3 supplier should be obtained by J.pplicant, or:

(b) Applicant should be required to obtain a contract to supply the above (satisfactcry to the 3 card, and Parties) which contains a clause that in the event GE ceases li353 4 '.1' ' l 'o e o-" g "y 1_ _4 a A. a"o c o s "e o- n o ' _4 ->

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than that available for such itecs frca U35S vendcrs in business at that tine.

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breaker systen nalfunction is the valves thenselves. Six va breaker v21v.es were found open in 1972 at Cuad Cities. Unit-2 deso_ite test D.ane) indication thc7 were " closed". . Intervenor contends Applicant cust ccanit itself to shutdown and insoection of these valves in event of containment spray operation. In ad-dition, Applicant should analyze all design based accidents uw- ,, .4 y- - ,

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aate of hot wall effect. Intervanor contends apolican"'s 2003 aust be of greste- capacity than the GZ33?.R indicates b a. c ' u s e o _f' -ha - u - -_.a ". 4 .,"> - m .' -v". 4_v m-

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Heat Renoval 3 7sten (RER) is an unnecessary risk to Interve'. or's t o ,...<v ., . . , l .z , o- -w, ua.n 01.-

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the critical reactor depressuricatica system, and an air coscressor s.7 stem or bottled cas crossun:. 3 / ate:, ?hich is unnecessaril7 v .

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be made sin.-le f ailure proof. fnat val'zes can be unreliaole is shown in ' V -0462 (July 1373) " Technical Report on Verating txperiences with SMR Pressure Relief Systeas." There have been 97 pressure relief valve f ailures in 10 years with 3dRS, inclu-ding 27 failures to open during operntion, 17 " potential fail-ures" to open, and 53 inadvertant openings. For these reasons o- -

Intervenor contends Applicant should be required to desien a sincie failure proof RHR systen.

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w4- .a .,5 dcy of .iay , fro' ilouston, Texas, to the artit - belo'.t. g\

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. . ' _ . ' . . . , , . ( 0_1) co'.forned copies were sent to .'.r. Chase 3terhens, Decketin n

.. 3 . n, _ .. ..v . ,, o. , q~.:.v 3he. don J. .olfe, 1sq. GiRC) n, r . -

Respectfully Submittei,C.'-l t

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Gustave. a. Linenber::er GIRC) '-

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