ML20136C878

Responds to Re Causal Relationship Between TMI Accident & Physiological Discomfort Experienced by Surrounding Population.No Determination Re Relevance of Issue to Restart Hearings

ML20136C878
Person / Time
Site:	Crane
Issue date:	08/31/1979
From:	Harold Denton Office of Nuclear Reactor Regulation
To:	Arnold L PARASCIENCE INTERNATIONAL
Shared Package
ML20136C883	List: ML20136C878 ML20136C892
References
NUDOCS 7910170429
Download: ML20136C878 (2)

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Dear Mr. Arnold:

Thank you for your August 2,1979 letter to Chaiman Hendrie in which you expressed your views on the causal relationship between the accident at

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.Three Mile Island Nuclear Plant-Unit 2 (THI-2) and the physiological dis-1 comfort and ill-health experienced within the surr6unding population.

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I' assure you of Chaiman Hendrie's interest in all aspects of the TMI accident, including any health effects. Considerable attention is being i

21ven by NRC and other Federal and State organizations to the broad range -

of health issues. The NRC/TMI Special Inquiry Group is reviewing informa-tion on radioactive releases and exposures from the accident an't will report to the Cormiission on its findings. NRC staff members'are actively '

participating in the Ad Hoc Interagency Task Group or: Dose Assessmer.t for THI. In' addition, the NRC/TMI Special Inquiry Group will be preparing a report oealing with non-radiological off-site impacts of the THI accident.

Various health studies sponsored by Federal, State and private agencies are being closely monitored and results available at the time the report is prepared will be treated in the report. These health studies will be monitored and will be evaluated to detemine the need for changes in NRC policy and procedures.

With regard to your concern about including psychological distress as an issue in the hearing on the restart of THI, Unit 1, the Commission has not q

yet detemined whether this, and related issues, can b6 legally relevant to the - hea ri n g.

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Harold R. Denton. Director "a3 9-Office of Nuclear Reactor Regulation '

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Dear Mr. Arnold:

tzgg i Thank you for yougd August 2,197 in which you expressed your views on the causal relaticrship between the accident at Three Mile Island Nuclear Plant-Unit 2 (TMI-2) and the physiological discomfort and ill-health experienced j

within the surrounding population, JJ U 'I O b s ". '. f. ' w /: rl 5

i I assure you of cy interest in all aspects of the TMI accident, including any health effects. Considerable attention is being given by NRC and other Federal l

and State organizations to the broad range of health issues. The NRC/TMI Special j

Incuiry Group is reviewing information on radioactive releases and exposures i

from the accident and will report to the Commission on its findings. NRC staff members are actively participating in the Ad Hoc Interagency Task Group on Dose Assessment for TMI. In addition, the NRC/TMI Special Inquiry Group will be preparing a report dealing with non-radiological off-site impacts of the TMl accident.

Various health studies sponsored by Federal, State and private agencies are being closely monitored and results available at the time the report is preoared will be treated in the report. These health studies will be monitored and will be I

evaluated to determine the need for changes in NRC policy and procedures.

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1 Mr. Larry E. Arnold l i

With regard to your concern about including psychological distress as an issue in the hearing on the restart of TMI, Unit 1 the Commission has not yet determined wnether this, and related issues, can be legally relevant to the hearing. In an Order and Notice of Hearing (Docket No. 50-229) dated 9

LN weewh August /1979, (copy) enclosed) the Commission called f orQnterested parties a

Luleva a r h thegppropriate Atomic Energy Act and National Environmental Policy Act issues.

Thank you for your interest.

Sincerely,

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JosepWHendri e Chairman -

Enclosure:

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Purpose:

. Approval, of en osed response.to a letter received.,,syg,;y,7 from<Mr. L. E. A nold Director,. Para Science,

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Dear Mr.:

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I-4 < ThaniQou.for 'your: letter; f?Augus,t 2;,1979;.inyh w

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,z-on the causal rel.at.i,ons. hip be een the acci. dest; at Three Mile,

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Plant-Unit 2 (TMI-2) and the phy iological discoqfort and ill' health experience,..

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and State organizations to the broad ~ range o health issues. The NRC/THI'Special '

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In addition, the NRC/THI. Special In uiry Group wil'l be preparing Assessment-for TMI.

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, Plan t-Uni t1;; (TMI 2); a nd' thes physiologita1^. discomfort and : ill'-heal th; exper

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In the Matter of METRCPOLITAN EDISCN CCMPANY Docket ?lo."50-2E9

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(Three Mile !sland Nuclear Station,

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Unit No. 1)

ORDER AND NOT!CE OF HEARING The Mett:palita'n Edison Cc:;any (the licensee) is holder of Facility 0:eratin; License No. CPR-5C gnich authqi:es the cceraticn of the nuclear power rea:::r kncwn as Three Mile Island Nuclear Stati:n, Unit No.1 (the facility or 2I-1), at steady state power levels not in excess Of 2535 megawatts themal (rated ::wer).

The facility is a Sabc0:k and Wil: x (33%) designed ;ressurt:ed -ater rea:::r (PWR) le:ated at tne licensee's site ten e.iles s:utheast cf Marristu ;, Fennsyl-vania.

II. On July 2,1979, the C:exissien ordered tnat the fac-ility re min in a : ld i.

shutdown conditien until further order of the C:=issien.and stat id t at a hearir; t

will be ::nducted ;rior to any restart of the facility. cn the isis of that l

hearing the C:=issi:n will detemine whether any fur;.er ::eration will be per-i

=itted and, if so, under wnat :nditions. The C =ission herein specifies the basis for its c:ncerns and the procedures to g vern further preceedin;s in this i

Catter. For the reasons later set forth, the Cet=issior, has determi d tha t l

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c satisfactory completion of certain short-tem actions and resolution of various concerns described herein are recuired to provide reasonable assurance that the facility can be Operated without endangering the health and safety of the public.

The Ccemissien has determined that certain additional long-term actions are, for the reasons given belew, required to be c:mpleted as prcmptly as practicable, and that reascnable progress on the' completion of such actions prior to restart is required, in order to provide reasonable assurance that the facility can be operated safely over the long tem. This Order and notice cf hearing further A

establishes procedures for a hearing and decision on the ;:nrticular issues identified in Section V of this Order. The Commission has determined that hearing and decisien with review thereof (as provided in Secticrts V and VI below) en the issues specified in this order is re;uired and that such hearing, decision and review on the issues relating to the actions required prior to restart of the facili,ty must be c:mpleted prior t: any Corrission Crder lifting the suspensien of operation.

Acccrdingly, the Atemic Safety and Licensing Board designated to conduct this pro-I ceeding sr.ould give priority to censideratien cf those issues which are related l

directly to sus;ension of operation. To the extent feasible, the Board shculd defer full review of the issues' related to the longer-tern actions until af ter the

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rendering of a partial initial decisien regarding the suspens en-related issues.

The Commissien's July 2,1979 Order recited that 'the Cer n'ssion presently lacks the recuisite reasonable assurance that the... License:'s Three Mile Island Unit No.1 Facility... can be cperated without endangering the health and safety of the public'.' Tne bases for that conclusion (which remains valid) are:

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3 in the c:urse of its evaluatien to date of the accident c the Three Mile Island Unit No. 2 facility, which utili:es a E&l! designed PWR, tne Nuclear Regulat:ry Commission staff has ascertained that E&W designed react:rs appear to be unusually sensitive to certain off-normal transient conditiens originating fn the secondary sys tem. The features of the 3&W design that c:ntribute to this sensitivity are:

(1) design of the steam generators :: coerate with relatively smail licuid volume in the secondary side; (2) the la:k of direct initiation c:f reactor trip upon the occurrence of off-nor al :enditions in the feedwater syste: ; (3) reliance en an integrated centrol system (ICS) to aut:matically regulate 'eedwate.r ficw; (4) actuation before reacter trip of a pilot-c;erated relief valve: en the primary system pressuri:er (wnich, if the valve sticks cpen, can aggrsvate the event);

and (5) a lcw steam generator elevatien (relative to the reacter v'essel) which provides a smaller driving head f a natural circulation.

3 Because of these features, E&W designed react:rs place mere relian.:e en.the i

reliability and performan:e chara:: eristics of the auxiliary feedwater system,.the 4

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integrated c:ntrol system, and the emergen:y ::re c cling system ( ECCS) perfcrean:e I to recover frem frecuent anticipated transients, such as less of e ffsite power an:. l I

loss of normal feedwater, than do other PVR designs. Tnis, in turn, places a lar;e l burden en the plant o;erators in the event of off-non al r.ystem behavior during su:h l anticipated transien.ts.

As a result of a preliminary review of the Tnree Mile Island Unit No. 2 accident chronology, the NRC staff initially identified several hurnan errors that cc:urred during the accident and c:ntributed significantly to its severity. All holders of _.

operating licenses, exce:t Vetropolitan Edison, wnese plants were riready shut-

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down. were subsequently instructed to take a number of ic= ediato actions to avoid

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1 4

repetition of errers, in acccrdance with bulletins issued by the Comissicn's Office of Inspection and Enforcement (IE). In addition, the NRC staff besan an immediate reevaluation of the design features of B&W reacters to determine whether additional safety ccrrections or improvements were necessary with respect to these reacters. This evaluation involved numerous meetings with B&W and certain of the l

affected licensees.

The evaluation identified design features as discussed above which indicated that E1W designed reactors are unusually sensitive to certain off-nomal transient conditiens originating in tne secondary system. As a result, an additional bulletin was issued by IE which instructed hoif.ers of cperating licenses fer B&W designed react:rs to take further actions, including i=ediate changes to decrease the react:r high pressure trip point and increase the pressuri:er pilot-cperated relief valve setting. Also, as a result of this evaluation, the NRC staff identified certain other safety concerr.s that warranted l

additional shcrt-tem design and crocedural changes at operating facilities having B&W designed reactors. These were identified as itens (a) through (e) en page 1-7

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of the'0ffice of Nuclear Reacter Regulation Status F.eport *.o the Cc=issien of I

April 25,1979.

I In addition to the items identified for the other S&W reacters, the unique circum-stances at THI require that additional safety cencerns identified by the NRC staff ~

be resolved prior to restart. These concerns result fr:m 51) potential inter-action between Unit 1 an.1 the damaged Unit 2, (2) questions about the canagernent capabilities and techni:al,rucurces cf Metropolitan Edison, including the impact of the Unit 2 recident on these, (3) the potentiaT effect of cperations 4

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S n;cessary to dec:ntaminate the Unit 2 facility on Unit 1. and (4) recogniced deficiencies in ecergency plans and station c:erating precedures. Based on the above, the Commission's Director of Nuclear Reacter Regulation (NRR) has recem-mended that the folicwing actions (the "short-term actions") be required of the licensee to resolve the cencerns stated herein and permit a finding of reasonable assurance that the facility can saf'ely resume operation.

1.

The licensee shall take the following actions with resrect to Ut!-l:

ta) Upgrade the timeliness and reliability of the Escrgercy Feedwater (EFW) j system by perforring the ite.ms specified in Enclosure 1 of the licensee's June 22,1979 letter. Changes in design will be subr5tted to the NRC staff for review.

(b) Develop and ieclement ocerating procedures for initiating and controlling ERl independent cf Integrated Control System (ICS)' ceritrol. ~

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1 (c) install a hard-wired centrol grade reacter trip on less of main feedwater and/or on turbine trip.

(d) Corplete analyses for pctential small breaks and develop and implement operating instru:tices to define operater action.

(e) Augment the retraining of all Peactor Operat:rs and Santer Reacter a

Operators assigned to the centrol roem including training in the areas of natural circulation and small break less of coolant accidents includ-

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ing revised procedures and the Tit!-2 accident. All cpera: Ors will also receive training at the E&W simulater on the Tlil-2 accident and tne licensee will conduct a 100 percent reexamination of all operators in these areas. NRC will administer complete examinations to all licensed

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personnel in acceedance with 10 CFR 55.20-23..

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6 2.

The licensee shall provide fer."RC review and approval of all applicable actic-specified in IE Sulletins79-05A, 79-053, and 79-05C.

3.

The licensee shall impreve his emergency preparedness in accorcance with the following:

(a) Upgrade emergency plans te satisfy Regulatcry Guide 1.101 with special attentien to action level criteria based on plant parameters.

(b) Establish an Emergency Operatiens Center for Federal, State and Local Officials and designate a locatien and an alternate location and pro-vide cor:munications to plant.

(c) Upgrade effsite monitoring capability, including additional thermo-luminescent desiteters er ecuivalent.

(d) Assess the relatienship of State /Lecal plans to the licensee plans so as to assure the capability to take emergency actions.

(e) Cenduct a test exercise of its emergency plan.

4 The licensee shall demonstrate that decentamination and/cr restoration cperations at TMI-2 will net affect safe cperations at *M!-1.

The licensee shall provide separatien and/or isclation of iMI ~1/2 radicactive liquid transfer lines, fuel handling areas, ventilation systems, and sampling ifnes-Effluent j

monitcring instruce.its shall have the capability of discriminating between I

effluents resulting from Unit 1 er Unit 2 eperations.

l 5.

The licensee shall demenstrate that the waste management capability, includir-stcrage and processing, for sclid, licuid, and gasecus wastes is adecuate to 4

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assure safe cperation of TMI-1, and tnat TMI-l waste handling capability is not relied on by operations at TMI-2.

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6.

The licensee shall cemonstrite his managerial :apability and resources *w operate Unit I while maintaining Unit 2 in a rafe ccnfiguration and carrying cut planned decentaminatien,and/or resteratien activities. Issues to be addressed include the adequacy of groups providing safety review and operatienal advice, the managerent and technical capability and training of operatiens staff, the adequacy of the cperational Quality Assurance pr:; ram and the facility pr:cedures. ;

and the capability of impcrtant supeert Organizations su:h as Health Physics and Plant Maintenance.

7.

The licensee shall dem:nstrate his financial :ualificatiens to the extent relevant to his ability to operate TMI-l safely.

S.

The li:ensee shall c:: ply witn the Categcry A rec:=encations as s;ecified in Table 2-1 cf NUREG-0575.

The Cc=issien has ad:.iti nal c: : erns, which, th: ugh they need not be resolved prior to resumptien cf c:eratien at Three Mile !sland Unit 1, nust be satisfac-l t:rily addressed in a timely canner. The Cor=ission's Director cf Nuclear Reacter

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a Regulatien (NRR) has rec:= ended the t the follcwing actions (the "leng-tem 4

actions") be required of the lice.see to resolve these c ncerns and pemit a finding of reascnable assurance cf the safety cf long-term operatien. These are:

1.

submit a failure mode and effects analysis of the ICS to the NRC staff as seen as practicable;

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give continued attention to transient analysis and procedures for management of small breaks by a formal crogram set up to assure timely actien of these matters; 3.

cceply with the Category B recommendations as specified in Table B-1 of KUREG-0578; and.

4 improve emergency preparedness in accordance with the fellcwing:

(a) modify emergency plans to address changing capabilities 1

of plant instrumentation, (b) extend the capability to take appropriate emergency actions fcr the population around the site to a dis-1 tance of ten miles.

III. Accordingly, pursuant to the Atomic Ener;y Act of 1954, as amended, and i

tne Ccemissien's rules and regulations in 10 CFR, it is hereDy crdered that:

(1) the licensee snall maintain PtI-l in a ccid shutde m conditien until furtner order of the Ccemissien.wnich will be issued follcwir; satis-j factory completion cf the recuired short-ter. actions and reascnable 2

progress teward satisfactory completien of those required long-term f

Actions referred to in secticn IV (such short-term and Teng-term j

actions to be censidered "recuired" for ::urposes of this clause which are detemined by the Cc= mission, after review of the Licensing Board's decisien, to be necessary and sufficient to provide adecuate crotection of the public health and safety); and 9

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(2) the licensee shall satisfactorily eceplete the leng-tem actions listed in Table 81 cf NUP,EG-C579 en the schedule set cut in such table and sucn other long-ter= actions listed abeve as promptly as practicable.

IV. The Commissicn has determined that, in light of !*:e concerns listed above, the public health, safety and interest recuire that the portion of the crder referred to in clause (1) of Section III shall Le irrediately effective. The long-term actions referred to in such clause shall be those long-tem actiens listed in section II as to which the Cor:nissien, prior to tne date of this crder, has issued irrediately effective crders against other licea. sees. If the Ccamission issues imediately effective orders against other licensees troosing requirements with respect to other long-term actions, it will, to the extent appropriate in the i circumstances, issue orders, effective i=ediately, to recuire that the licensee demonstrate reasonable progress t: ward cecoletien of such other acticas as a condi-tion to restart. If the Eccrd cetemines that operaticn can be resured upen c'emple-l tion of certain s;ecific short-te n actions by the licensee, it shall censider the extent to w,ich the licensee has cemerstrated reasonable progress toward completien I of the long-term actions described in this section. If it finds that the licensee has denenstrated reasonatie progress, it snall recommer.d resumptien of cperation upon completien cf the short-tem actions. If it cannot rake such a finding, it shall recommend that operation be resumed at & date that it believes approcef ataly ]

I reflects the importance of the action involved, the ti: e lost because such progress l had not been made on the prescribed schedule and tae overriding need to provide adequate ;rctection for the public health and safety.

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An Atomic Safety and Licensing Board censisting of Ivan W. &nith,

_sc., Chair-man, Dr. Walter H. Jordan, Member, and Dr. Linda W. Lf ttle, tiecter, f s hereby established to rule on petitions to intervene, to c:nduct the hearing ordered herein, and to render an initial decision in acc rdance with 10 CFR 2.760. Tne Atomic Safety and Licensing Board will issue a further ceder specifying the date and place of the hearing and any prehearing c:nferences. The Board should hold its. sessions in the vicinity cf the facility and it should attempt to schedule some of its sessiens in the evening or on weekends to permit the raximum p:ssible public attendance.

The hearing will be conducted in acc rdance with the applicable pr: visions of subcart G of the Commissien's Rules of Practice set forth in 10 CFR Part 2.

Tne provisions of 10 CFR 2.715a (censolidation of parties), 2.751a (special prehear-ing c:nference and order), 2.752 (prehearing c:nference and order) shall 4: ply to this proceeding.

The Ccemissien's primary commitment is to a fair and thorough hearing and decision.

Given tnis overriding imperative, it is the Ocmission's ex;ectati:n that the Board will c:nduct the proceeding exceditiously. Tne Scard sh:uld as early as possible publish an appropriate schedule and attempt to meet it. A tentative schedule corposed by the Commission is attached f:r the Board's pessibie use, although the Scard should not be c:nstrained by it. The Soard is instructed to explore c::crtunities to shorten the time limits provided in the Rules pursuant I

to 10 CFR Z.711. The Licensing Board is hereby instructed to c:ns:lidate participation of parties pursuant :: 10 CFR 2.7154 to the maxieum extent prac-ticable consistent with the provisions of that regulation. In its review cf the Initial Decision, the Commission will invoke 10 CFR 2.711 to snorten ::ime limits j

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i 11 where feasible. It is hereby directed, pursuant to 2.760(a), that, upon issuance of the initial decision (or partial initial decisien) in this matter, the record be certifled to tne Commission itself for final decision. Any party may take an appeal directly with the Ccmmission by filing exceptions to the initial decisten (or partial initial decision) in accordance with the provisions of 10 CFR 2.762.

Ccemissien review of the initial decision will be cond::cted in accordance with 10 CFR 2.772.

In the conduct of this preceeding the Licensing Scard should exercise its authority to seek t: ensure that it receives all infomation necessary to a thorough investi-gation anc resolution of the questions before it. However, it should use its authority under 10 CFR 2.757 to prevent any undue delay to the proceeding resulting from any cress-examination not required for the full and true disclosure of the facts or free ocher sources mentioned in that section.

i The provisiens for pre. hearing discovery set forth in 10 CFR 2.740-2.742 shall acply t: 5.'sproceeding. Furthermore, in several locations, including the Cc. -

-issien's P b:ic :ocument Poem and the Tli! Local Cocument Room in Harrisburg, the l

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j lcmmissicr. wi'l maintain and continuously uodate a cecotlation of all publicly tva11able inferration on the Three Mile Island accident and related matters, and it will als: cermit infomal access to NRC staff considerations of the issues e

involved in t.iis hearing in the manner in dich such access is permitted in react:r licensing proceedings. It shall be an adequate respense to any cis-ccvery recuest to state tnat the information or document requested is available in the ;ctlic compila:1on and to :rovide sufficient infoma icn to locate the document er it.fer: ation. Foreover, as provided by 10 CFR 2.740(c) and 10 CFR l*s..

12 2.740(d), the licensing board may and should, when not incensistent with fairness to all parties, limit the extent er centrol the secuence of discovery to prevent undue delay or imposition of an undue burden on any party.

The subjects to be considered at the hearing shall include:

(1) Whether the "short term actions" recommended by the Director of Nuclear Ceactor Regulation (set forth in Section II of this Order) are necessary and sufficient to provide reascnable assursnce that the Three Mile Island Unit 1 facility can be operated without endangering the health and safety of the public, and should be required before resurption of cperation shculd be permitted.

(2) Whether the "long-term actions" reccmmended by the Directtr of Nuclear Reacter Regulation (set forth in Secticn II of this Order)

I are necessary and sufficient to provide reasonable assurance that j

the facility can be operated.fer the long tern withou't' endangering i

the health and safety of the :ublic, and shculd be recuired of the licensee as seen as practicable.

j As to the issue of financial qualifications mentiened above, a party wishing to raise this subject as a contention must clearly indicate why the licensee's finan al c nditien might undermine the licensee's ability to cperate the plant safely. Parties raising this issue should do so before the 5:ecial Prehearing Conference.

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'Taile real and substantial c:ncern attaches to issues su:h as psychological' distress and others arising from the continuing impact of aspects of the Three Mile Island accident unrelated directly to ex;csure to radiation en the part of citi: ens living near the plant, the Commission has not detemined wnether such issues can legally be relevant 'to this proceeding. Any party wishing to raise suca subjects as cententiens, or as aspects of separate contentions, should brie" the Atomic Energy Act and National Environmentai Policy Act issues 1e believes a:pr::riate to the Beard as part of the' contentien acceptance process set out in the Cor. mission's regulations. The Board should t.en certify such t

issues to tre C m-ission for final decision prior to the issuance of its pre-nearic; ::n'erence crder ;ursuant t 10 CFP. 2.752(c), either with or without its

-e::rendat' n en suca issues, as it deems appr:priate under the :ir:umstances.

At the tire the C:mmissien reaches a decision en these issues, it will also cen-sider whe:ner it can and sh:uld grant financial assistan:e to parties seeking to i

raise these issues in this case.

• at'sfa':::ry ::x pletion of the requirec actions will be cetermined by the Direct:r f

f 'uclear Feacter Fegulatien. However, ;rier to issuing its decisien the 5 card 6

l shall have authority to require staff tc inform it cf the detailed steps staff l

elieves necessary to implement actions the Scard may recuire and to approve er disapprove =f the adequacy of such measures. With respe:t to any uncompleted

'ter s the 3 card shall have authority similar to that provided in 10 CFR 50.57(b) l

take s:::t acticns or :: impose such limitations er c:nditions as it believes t

re:essary :: ; rete:t the public health and safety: Provided, that, as previded e

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14 elsewhere in ti..s order, restart shall not be permitted until satisfactory com-pletion of all uncompleted shor+-tem actions. Any affir=ative detemination by the Direct:r will be based upon his finding that the actions specified by the Board, er by the Commission on review, have been taken, that the specified implementing procedures employed are apprcpriate, that the licensee satisfies the financial qualification criteria imposed on an a;plicant for an cperating license, and tnat there is reasonable assurance that the facility can safely resume opera-tion.

As noted above, the Atomic Safety and Licensing Scard sneuld accord priority to the censideration of matters relating to the need fer continued susper.sion of operating authority. Vithin the limitatiens of 10 CFR 50.59 and ".717(b) of the Cemnissien's regulattans, the licensee may commence ecdifications, such as those i

recommended above by the Director of Nuclear Feactor Regulatien, during the pendency cf this proceeding at its cwn risk.

VI.

If the Licens'ing Board should issue a decisien authori:ing resumption of operatien upon completion of certain short-tem actions by the licensee and a l

finding that in its judgment the licensee is making reasenable progress tcward I

cmpletion cf the long-tem actions specified in this order as to which the Cee-mission has issued immediately effective crders against other licensees, and subsecuently if staff certifies that those shcrt-tem actions have been ccmpleted to its satisfaction, the Ccmmission will issue an order within 35 days after such certification deciding whether the provisien of this order requiring s.-

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15 the licensee to remain shut down shall remain immediately effective. Any motions relating to the lif ting of immediate effectiveness must be received by the 1

Secretary of the Commission within 10 days of issuance of the certification, and any responses to such motions must be received by the Secretary 7 days later.

The Commission shall issue an order' lifting im ediate effectiveness if it determinej that the public health, safety or interest no longer require ir. mediate effective-ness. The Commission's decision on that question shall not affect its direct appellate review of the merits of the Board's decision.

VII. By Sectember d,1973, the licensee may file a written answer to this Order and any person whose interest r.ay be affected by tnis prcceeding may file a written petition to intervere. Petitions for leave to intervene must be filed in accordance with th,e Ccmmission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.

If a petitien for leave to intervene is filed by the above date, the Atomi: Safety and Licensing Board established by this Order will rule on the petition and issue an appropriate further order. An order f.

anelly deryin; a petition for leave to intervene shall be appealable by the l

petitioner to the Commission itself within ten days af ter service of the order.

An order granting a petition for leave to intervene shall be appealable to the Commission itself by a party other than the petitioner on the cuestion of whether the petition should'have been wholly denied.

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As recuired by 10 CFR 2.714, a petition for leave to intervene shall set forth j

with particularity the interest of the petitioner in the proceeding, and how O

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16 that interest may be affected by the results of the preceeding. The petition should specifically explain the reasons why interventien should be permitted with particular reference to the folrowing factors:

(1) the nature of the petitiener's' right under the Atomic Energy Act to be made a party to the proceeding; (2) the nature and extent of the petitiener's preserty, financial, or other interest in the preceeding; and (3) the possible effect of any crder whien may be entered in the proceeding on the petitiener's interest.

The petitice shculd identify the s;ecific aspect (s) of the subject matter of the proceeding as to which petitioner wishes te intervene.

i Not later tnan fifteen days prier to the first prenearing conference sc.9eduled in

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the preceeding, the petitioner snall file a suppler.ent to the petitien to inter-vene which must include a list cf cententiens which are scught to be T itigated in the r.atter, and the bases for each concern set forth with reasonable specificity.

A petitiener who fai.ls to file such a supplement wnich satisfies these require-cents with respect to at least one centention vill not be permitted to participate as a party.

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i 17 An answer to this Order or petition for leave to intervene should be filed with the Secretary of the Commission,.U.S. Nuclear Regulatory Comission, Washington, D.C. 20555, Attention: Docketing and Service Section, er r.ay be delivered to the Cc= mission's Public Document Room,1717 H Street, N.W., Washington, D.C. by September 4,1979. A copy of the petition should be sent to the hecutive Legal Directer, U.S. Nuclear F.egulatery Cocmission, Wasnington, D.C. 20555 and to Mr.

George F. Trowbridge, Shaw, Pittman, Pcits and Trewbridge,1800 M Street, N.W.,

Washington. 0.C. 20036, attorney for the licensee. Any :;uestions or recuests for additional infer ation regarding the content of this '6tice should te addressed to the Chief Mearing C:unsel, Office of the Secutive Legal Director, U.S. Nuclear Regulatory Cc=ission, Washington, D.C. 20555.

Nontimely. filings of 1:etitions for leave to intervene, arended petitions or supplemental petitions will not be entertained absent a cetermination that the petitioner has made a substantial shewing of goed cause f:r the granting of a later petition. Tna ceten-inatien will be based en a baiancing of the facters specified in 10 CFR 2.71a(a)(1)-(v) and 2.714(d),

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i VII. Copies of tne fellowing documents are available for inspection at i

the Commission's Public Occument Room at 1717 H Street, N.V., Washingten, D.C.

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and are being placed in the C:sissien's local public doct: rent reem at the State Library of Pennsylvania, Government Publications Section, Education Building, Cc=cnwealth and. Valnut Streets, Harrisburg, Pennsylvania 17125.

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August 1 Commission Order April 16 Ltr. Hertein to Centon (prior notice will ce given before restart)

June 23 Ltr. Hertein to Cent n (modifications to be c:mpleted before mI-1 restart)

June 28 NEC Staff Meeting su::: ary on THI-1 restart NUREG-0578 I&E Bulletins79-05A 79-058 79-05C For tr.e Comissicn i

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5AFUEL J. Ce.L:,

Secretary of tt.e ::=fssicm i

Dated at "ashington, D.C.

this 9th day of _aurust

. 1979.

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Time Consumed Total Oays nto Mil es t:ne (Days)

Proceeding 0

0 Publicatien of Notice (Detailed Order) 20 20 Filing of Intervention Petitions Answers to Petitions 15 35 Time for icending Pe titions 25 60 and for Negotiations re Contentions Time between filing teen::ed 15 75 Petitions and Contentions and Special Frenearing Conference Publication of Special Prenearing 5

80 Conference Order (Discovery tegins)

Discovery ecmpleted 60 140 During discovery peried:

-Objections to Special Frenearing Conference Orcer,10 days

-PCssible further refinement of contentions i

140 Prehearing Conference Prehearing Conference Orcer 5

145 20 165

/

Filing of Testimony (Assumes objectiens to Orchear-i ing Conference Creer filed simultaneously)

Begin Hearings 15 180

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Complete hearings

- 60 240 I

Filing of Prcoosed Findings 40 280 Reply to Proposed Findings 10 290 Decision by Board 45 335 O

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'No 79-2291 s/7/79 to,,, o.,e NRC SECRET ARIAT h Communener To-04:e N t3 E sec. Der /Oper O c.n. coun i O co% t son O ss. io, O Puble Affaers O secreierv O

Larry Arnold, Director Para 5cience International Chairman Hendrie g,,,8/2/79 ro.

re the accident at TMI [NPC's concerns.

suoiec, pmntinnal.. Dhysical conditions of pMple withe ~

l the TMf area etct) 1 Xh Prerwe repay for segnaturn o,. Aug: 17 5D Chairman O com.mnar O f oo. oc. ct. sot. F A. secy O s.gn. ore o oci om.ned 0

Xd Return original of incoming with responu r'"~~

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• send mree c) copies of ven#v to secy Ma.i Faciliiy ACTION SUF I