ML20081A501

Petition of Save the Valley for Leave to Intervene,Listing 15 Contentions Re Integrity of Concrete in safety-related Structures,Electrical Work,Evacuation Plans & Common Mode Failures.Certificate of Svc Encl

ML20081A501
Person / Time
Site:	Marble Hill
Issue date:	10/21/1983
From:	Cassidy H SAVE THE VALLEY - SAVE MARBLE HILL
To:	NRC OFFICE OF THE SECRETARY (SECY)
References
NUDOCS 8310260291
Download: ML20081A501 (6)

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, T COLMEirt BEFORE THE SECRETARY OF THE COMMISSION Ug;Rf 0F THE UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 .'83 00T 24 P12:19 IN RE: 'fME MARBLE HILL NUCLEAR ) DOCKET NOS. STN $dk.5-hg U y[;

OPERATIEG STATIONS, UNITS 1 & 2 ) STN 547 B M;CF SAVE THE VALLEY'S PROVISIONAL CONTENTIONS

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1. Integrity of concrete in safety-related structures is not assured.

This follows from the tectimony en quality control in the "Itcarings beferc '

a Subcommittee of the Committee on Government Operations, !!ouse of Representatives, Ninety-Sixth Congress, First Session, November 27 6 28, 1979".

2. Reverification of concrete integrity in saf et y-relat n! structures resultant from the 1979 work-stoppage in these areas is callei into <;uestion by alleged falsification of quality control records.

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3. The integrity of electrical work perferned by Ccermeeveal:5 Lerd - Joint Venture and other subcontractors is not assured. Ste-1ftra117 ?.st troter category 1 material has not been used in hangers and other insta11stice.s rur suant to and in conformity with relevant NRC and national professional testa!!at ten rcAulations.

4. There he.s been non-conf ornit y vtt'u the KRO auf r elevast rentattees respceting the docunentation of cicctrical work, exposrd by the Ja .ary, 1953 cessation of work in saf ety-related areas and raining intertant r.c c: tenn. (See Contention 3).

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5. Neither Public Service Indiana (PSI) nor the staff has presented a meaningful assessment of the risks associated with the operation of the Marble hill facility including, and over and above, the non-compliance in safety related structures noted in Contentions 1 to 4, the staff still seems to regulate upon the basis of the Rasmussen Report although in view of the Lewis Committee findings these led NRC to withdraw official reliance on that prior report. The Commission has stated that it "does not regard as reliable the Reactor Safety Study's numerical estimate of the everall risk of reactor accident". I (NRC statement of Risk Assessment and the Reactor Safety Study Report (Wash - 1400) in Light of the Risk Assessment Review Group Report, January 18, 1979.) The withdrawal of NRC 's endorsement of the Reactor Safety Study and its findings leaves no technical basis for concluding that the actual risk is low enough to justif y operation of Marble Hill.

6. There is no basis for concluding that the design of Marble Hill provides protection against so-eslied " Class 9" accidents. There is no basis for concluding tha t such accidents are not credible. The staff has conceded that the accident at Three Mile Island (TMI) falls within that classification. .Ther efor e, there is net rea sonable a ssurance that the Marble Hill facility could be operated without endangering the health and saf ety of the public. (See also Cont ent ion 5. surra.)

7. No adequate evacuation plans for Marble Hill exist. Neither on the Indiana

-side nor on the adjacent Kentucky region across the Ohio River from Marble Hill are there credible plans for evacuation syste=s. Moreover, the example of events at TMI showed the inadequacy of NRC emergency planning requirements. Plans for evacuation should be based on worst-case analysis of the potential accident a

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l consequences of a core melt with breach of containment (Contentions 1 & 2 are relevant her a) s Publ.ic health and saf ety requires that prior to the operation of Marble Hill there be in place an ef fective, well publicized and tested plan to evacuate the public in the event of such an accident. There is no adequate emergency plan for evacuation 'of Marble Hill based on a weather-dependent wor st case analysis of the potential consequences of a core melt with breach of containment.

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8. No adequate plans exist for all of the areas which could potentially be at risk in a nuclear accident. Since studies of the AEC-NRC (including k' ASH-740) indicate that radiation releases could' impact as far as 100 miles, and in light of the fact that radiation releases, airborne and through ground water, from the at cident at TMI impacted far beyond the EMZ, emergency plans for Marble Hill must take account of an at es within a radius of 100 miles from the plant site. This area includes, within the State of Indiana, Bloomington and Columbus, and in Kentucky, Louisville, each being substantial population centers.

9. Common mode failures have not been adequately addressed by NRC or l'SI.

As one specific example, because of the nearnes 3 of the New Madrid fault with its known potential for earthquake behavior, ther e is a legitimate questio. concerning the ability of Marble Hill to maintain its structural integt-ity in the event of g

this corcon mode occurrence.

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10. No adequate assurance has been given by PSI and NRC that the cle ::...

systems in saf ety-related areas are mechanically sound. A Confirmatery Actica i I

Letter (CAL) sent to PSI by NRC, February 2,1983, gives the public so=c infer :.at te, i on the type, depth and extent of the problems verified by NRC during the special inspection they conducted January 24-28, 1983. CAL mentions that "the stop work ),

encompasses fabrication and installation of electrical auxiliary steel; cable tray i i

and conduit hangers; and cable tray and exposed conduit. The word ' fabrication'

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hecein suggests, in the light of non-conformance in documentation (Contentions 38 f, and 4), that the quality of materials as well as of the electrical work may be k i

unknown. We recall here that one of the major problems in the Brown's Ferry accident h originated in the cable trays, i

11. Inherent in the nuclear fission process is the production of a high flux of neutrons. This flo.i of neutrons causes some transmutations to occur within the metal structures of all nuclear plants. Because this inherent problem has not been adequately addressed by NRC, the Marble Hill plant must not be allowed to opcrate.

12. 1 SI has had in " storage" many of the saf ety related components of proposed reactor s. These components are in some respect out of date and should not be counted in the Marble Hill reactor units.

13. The NRC Steam Generator Status Report of February,1982 (SECY 82-72) acknowledges that no eff ective solution has been found for prevention of stes=

generator tube degradn't' ion whence we contend that Marble Hill should not be allowed to operate.

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14. The Westinghouse D-Series models of steam sencrat or s . . ;.: .s f., F,.

F.arble Hill have had excessive vibration proble=s which can a N.:.:u. b y

generator tube integrity. These which lead to derating (at the 1 .

generators, thus increase the eff ective cost of the plant. Nm y ,g g , ,

l irpair the saf ety of the plant, and require that such equipment e-. .

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15. It would be imprudent to license another nuclear plant to c:no s e why - to

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the technology of decomissioning, and its cost, ha s b een d e=on ett.g .: ,,s (ty. ' .

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reactor, and until there is provision for ultimate disposal of its taita,g;..

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, n Save the Valley reserves the right to add, subtract and/or coatt; t he s te e g.

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I list of Contentions and respectfully submit to the NRC that sa:e are 1 a : s.; f s;.or  ;

,{n today because time may be of the essence. ., i F

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HAROLD G. CASSIDY 6 TRD l'.Lirf. Q, ,; )

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THOMAS M. DATTILO ATTORNEY AT LAW c

%4' 211 EAST MAIN STREET MADISON, INDIANA 47250 .

- fji PHONE: 812-265-6355 Q CERTIFICATE OF MAILIN_C

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or The undersigned certifies that on this 21st day of N" *1*#

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'l cause to be mailed by certified mail - return receipt. * *T*M The Valley's Provisional Contentions. , j -

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Jon D. Noland, Esq. 0

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Senior Vice President and General "I b Counsel G'"*"'I DE-Public Service Company of Indiana Wabash yal. it' - e~

1000 E. Main Street p , o , g;, Mi ." '.; * 4 m m > .4, g 4 P1,ainfield , Indiana 46168 722

1. 1. 1. # M Indiana el .. I. na . .

tmg Mr. William Kortier Mr' J***' -

Water Reactor Division Westinghouse Electric Corporation .

U. S. NRC,tr.e;e ".N '.. . Ns P. O. Box 3eo, 799 Roosevelt :T.7 ' ' .

Pittsburgh, Pennsylvania Gl e n Eli# " ' ' ' ~" W 0" M 15230 .- i 4

Mr. P. L. Wattelet Don F. Morton r.-

Sargent & Lundy Engineers General Counsel' = k Wabash Vall #h' 55 East sonroe Street Chicago,' Illinois 60603 P. 0.' Box 2, c W'% 3b '

722 North High ::.g.;t g Indianapoits, .: % tg g 1, .

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Harry H. Voight, Esq. .

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. LeBoeuf, Lamb, Leiby & MacRae Mr. Tom Zeller 1333 New Hampshire Avenue, N. W. - 5p.

Washington, D. C. Vice President -

20036 Val l ey Wa tc h , t r.: .

Thomas M. Dattilo, Esq.

P. O. Box 2262 Evansville, Instana C14

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i 311 East Main Street C

Madison, Indiana 47250 Mr. Fred Hauck b,.

President ,

Louisville Water Company Save the Valley, ' n: . 'Ji k ATTN: Mr. Stephen A. Hubbs R. R. i3, Towers htt;*t Environmental Engineer Shelbyville. Lectudy C*At -

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435 South Third Street k.

Louisville, Kentucky 4'0202 Ms. Mary Pat Lyn:h '

President '

Mrs. David G. Frey Sassafras Aududen So;tet,r -.

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Sassafras Audubon Society 605 South Fess Ave' t. 41.

2625 S. Smith Road Bl oo mington, f r.3 t e r.s .i.gn ,

C 8 ft; f f M; Bloomington. Indiana 47401 pr. oscar H. Tar t e At o=ic sa f e t y a L n o"?W W W W;W i -

'Nk Mr. Jerome F. Schapker u. s. rac .. f U. S. Nuclear Regulatory Commission y3,3s,-stee, :p.G .W. .!).) l 5M.' g;f .

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Resident Inspectors Office

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Ivan W. Smith, Chairman, Atomic Saf ety 6 Wa shinnt en. 0 ', * ' '

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U.S. NRC .

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