ML19209B212
| ML19209B212 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/09/1979 |
| From: | Chilk S NRC OFFICE OF THE SECRETARY (SECY) |
| To: | METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19209B210 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 7910090333 | |
| Download: ML19209B212 (19) | |
Text
s UNITED. STATES OF AMERICA NUCLEAR REGULATORY C0"SISSION COPEISSIONERS:
Joseph M. Hendrie, Chaiman Victer Gilinsky Richard T. Kennedy Peter A. Bradford John F. Ahearne
)
In the Matter of
)
)
l'ETRCPOLITAN EDISON COMPANY Docket F:o. 50-259 (Three Mile Island Nuclear Station,
)
Unit Mo. 1)
ORDER AND NOTICE OF HEARING I.
The Metropolitan Edison Company (the licensee) is helcier of Facillity Operati-License t'o. DPR-50 which authorizes the operation of ts. r.uclear poveer reactor known as Three Mile Island Nuclear Statien, Unit No.1 (t.te facility or TMI-1), :
steady state power levels not in excess of 2535 megawatts thernal (rated power,).
The facility is a Sabcock and Wilcox (B&W) designed pressetrized water reacter
'(PWR) located at the licensee's site ten miles southeast of Harrisburg, Pennsyl-vania.
II.
On July 2,1979, the Ccc=ission crdered that the facility re...e in in a colc shutdown c:nditicn until further crder of the C:: issi:n <and stated that a hear" will be c nducted prior to any restart of the facility.
On the basis of tha rearing the Commission will de:cmine v, tether any furt..e 0:eratien will be ;er-
"- e: anc, if so, ur. der ahat condit cns.
ine C:=issi:n herein specifies the
~
asis f:r i s concerns and tne pre ecures to grvern fur:f.er prc:eedir.gs in this
-.a :p.
- r the reas:ns later set fcrth, the C:=issi:n nas detemined tha nr lll3 U
791009033 3 rncicsure 1
000R DEL satisfactory completion of certain short-tenn actions and resolution cf varicus concerns described herein are required to provide reasonable assurance that the facility can be operated without endangering the health and safety of the public.
The Commission has determined that certain additional long-term actions are, for the reasons given below, required to be ccmpleted as promptly as practicable, and that reasonable pr gress on the ccmpletion of such acticns prior to restart is required, in order to provide reasonable assurance that the facility can be operated safely ever the long term.
This Order and notice of hearing further establishes precedures for a hearing and cecision :n the ; articular issues identified in Section V of this Order.
The Commission has deternined that hearing and decision with review thereof (as provided in Sections V and VI below) on the issues specified in this order is required and that such hearing, decision and review on the issues relating to the actions required prior to restart of the facility must be ecmpleted prior to any C:mmissicn Crder lifting the suspension of operation.
Accordingly, the Atomic Safety and Licensing 5:ard designated to conduct this prc-ceeding should give priority to consideration of these issues which are related diregtly to suspension of operation.
To the extent feasible, the Scard should defer full review of the issues related to the lenger-term. acticns until after ne rendering cf a partial initial decision regarding the sus:ensicr.-related issues.
Tne C: mission's July 2,1979 Grder recitec that "the C mrissicn presently lacks t e s:Lis'te reastrable assurance tnat tne... 'icensee's Th ee File Islard arit *. l Facility..
Can b2 cperate: h#:bCJ: en ange~ing the healtn and sa#i 0
tr
- ubli;."
70s bases for that
- nClusi0n (-Pich re a'ns valid) a e:
?
"nf J
V
3 '
PDDR ORBIML In the course of its evaluation to date of the accident at the Three Pile Islar.d Unit No. 2 facility, which utilizes a S&W designed FWR,.the Nuclear Re;ulatory Ccemission staff has ascertained that P&W designed reacters appear to be unusuall.
sensitive to certain off-normal transient conditicns criginating in the se:endar;-
'sys tem.
Tne features of the B&W design that contribute to this sensitivity are:
(1) design of the steam generators to cperate with relatively small liquid volcr.e in the secondary side; (2) the lack of direct initiaticn of reacter trip upon the occurrence of off-normal conditions in the feedwater systec; (3) reliance On an intecrated centrol systen (ICS) to automatically regulate feedwater flew; (4) actuation before reactor trip cf a pilot-perate: relief.ralve on the pri: a ;
system pressuri:er (which, if the valve sticks c;en, can aggnavate the event);
and (:i) a low steam generator elevation (relative to the rea 'cr vessel) which provides a smaller driving head fer natural circulation.
Because cf nese features, S&W designed reacters place rare rtaliance on the reliability and performance characteristics of the auxiiiary -feedwater system, th integrated centrol system, and tne emergency core cooling :ys-tem (ECCS) perfer cr to recover from frequent anticipated transients, such as less of offsite power ar
- 1. css cf no nal feedwater, than do other M!R decigns.
Tnis, in turn, places a lar burden on the plant operators in the event of off-normai system behavior during :
anticipated transients.
As a result of a preliminary review cf t~e I9 Fee ile Island Ur.it
- c. 2 1:~icer.:
- - Or.:l:gy, Ine.GC staff initially ider.ti'ie: several tran errcrs that :::u-e CU #"; l'"e a ~ ice".t an nt[icute: sic"'fiCantly 0; its seVEarity.
All '.: :e ;
- e- ^.im; :e ses, exce:t etr::clitan E:isen, w'ese plants were already shut-00..n, e.ere s'.:se:ue"tly i~structe:
C take a nu rer Of ir; ediate actions 0 a.:-
117 "n7 I I
).
i
4'
?00RBRGlWLI repetition of errors, in accordance with bulletins issued by the Co :.ission's Office of Inspect.an and Enforcement (IE).
In additi n, the NRC staff began an immediate reevaluation of the design features of B&W reacto rs to determine whethe-additional safety corrections or improvements were necessa: y with respect to thest reactors.
This evaluation involved numercus testings with.31W and certain of the affected licensees.
The evaluation identified design features as dis:ussed above which indicated that E&W designed reactors are unusually sensitive :: certs in off-ncr.al transient ccnditions originating in the se:ondary syster.
Is a result, an acditional bulletin was issued by IE which instructed hoide s of cperating licenses for E&W designed reactors to take furcer acticns, including immediate chances to decrease the reactor high pressure tri point ar.d increase the pressuri:er pilot-operated relief valve settinc.
Al s o,.as a result of this evaluation, the NRC staff identified certain other safety cancerns that warrante:
additional shcrt-tenn design and procedurai charges at oper ating facilities havir; E&W designed reactors.
These were identified as items (a) -through (e) on pace 1 -
of the Office of Nuclear Reactor Regulation Status Report to the Cone.ission of April 25,1979.
In additi:n to the items identified for the Other E&V reacters, the unique circ:.-
stances at TMI require that additio' '.1 safety : ncerns ide tified by the NRC sta#
be res:1ved pri:r to restart.
1mese concerns result fr:- '1) potential inte -
a:-i:
- e:ees* Unit i and the dama;ed Unit 2, (2) :;esti:nn about the anagere :
a:a:":ies a.
technical reS0urces Of ".e:r ::litar Ecis01, inclucir.; the
'.:a:: :#
re.ri: 2 a :ident on these, (3) -be :: en ial affect Of c:eratiens 1113 f3
?00R ORGINAL necessary to de: cntaminate the Unit 2 facility on Unit.1, and (4) reccgnized deficiencies in emergency plans and station c;eratinc precedures. Based on the above, the Ccamission's Director of fluclear Reacter Re;ulatica (fiRR) has recem-
= ended that the follcwing acticns (the "short-term actions") be required of the li:ensee to resolve the concerns stated herein and pemit a finding of reas:nable assurance that the facility can safely resume operatien.
1.
The licensee shall take the following actions with respect to TMI-1:
(a)
Upg-ade tne timeliness and reliability cf the Emsr;ency Feec~ater (ER.')
system by perfoming the items specified in Encl sure 1 of the liter.see's June 25,1979 letter.
Changes in design will 'ce subritted to the tiRC staff for review.
(b)
Cevelop and implement operating precedures for initiating and centrolling EFJ independent of Integrated Control System (ICS) control.
(c)
Install a hard-wired control grade reacter trip cn icss of tain feedwater and/or en turbine trip.
(c)
Complete analyses for potential small breaks and develcp and inpiement operating instructions to define operater action.
('e). Augment the retraining of all Reactor Operators and Senior Reactor Operators assigned to the control rec: including training in the areas of natural circulation and small break 1:ss of c:clant accidents includ-ing revised prccedures and the FI-2 accident.
All c;eraters will als:
receive traininc at the En' simulat:r en the ?.~-2 a:ci:ent and the
:enses,.ill ::nda:
a 1C0 :ercent reexa-i at':- :# al' 0;e r a : s -; n
- .ese a eas.
N:.C wi'i ahminister ::mplete exa '.aci: s :
all licer. sed ers:- ei in at:: :an:e witn 10 CFE 55.20-22..
1117 nn i I 1,)
P00R ORCNM 2.
Tne licensee shall provide for iRC review and approval of all applicable acti:
specified in IE Bulletins79-05A, 79-055, and 79-05C.
3.
The licensee shall improve his emergency preparedness in accordance with the follcwing:
(a)
Upgrade emergency plans to satisfy Regulatory Guide 7.101 with special attentien to action level criteria based en plant paniceters.
(b)
Establish an Emergency Operations Center for ~eceral, State and L cal Officials and designate a iccation and an alternate Toca:icn and :r:-
vide cenmunications to plant.
(c)
U: grade offsite monitoring capability, including additional therm -
luminescent dosimeters or ecuivalent.
(d) Assess the relationship cf State / Local plans to the licensee ptans so as te assure the capability to take emergency actions.
(e) Conduct a. test exercise of its emergency plan.
4 Tne licensee shall demonstrate that decontamination and/or restoratien o.perations at TMI-2 will not affect safe cperations at TMI-1.
The '!icensee shall provide separation and/or isolation of TriI 1/2 radioactive liquid transfer lines, fuel handling areas, ventilation systems, and sampling lines..
Effluent monit:rinc instruments shall have the capability Of districinating be: ween effhents resultinc fr:m Unit I cr Unit 2 Operati:ns.
5.
-te ' ice.see shall cem:nstrate ina: :ne -aste managemen capa:i l':y, i.:1.:-
s :Ta;e a~.: :r; essiSS, fCr sClic, 'i ui, ar: Case us AEstes is ad e:. ate ::
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P00R ORG NM assure safe operation of TMI-1, and that TMI-1 waste handling capability is not relied en by operations at TMI-2.
6.
The licensee shall cemonstrate his manageriaT capability and rescur:es ::
cperate Unit I while maintaining Unit 2 in a safe configuratien and carrying cut p'lanned decentamination and/or restoration activities.
Issues to be addressed include the adequacy of grcups providing safety review and operational advice, the management and technical capability and training of operations staff, the acecuacy of the c eraticnal Quality Assurance pr: gram and the facility precedures.
and tne capability of im;0rtant su; port crgani:ati:ns su:h as Healin Physi:s an:
D'. ant F.aintenance.
7.
The licensee shall demonstrate his financial ct.,alifications to th a extent relevant to his ability to operate TMI-l safely.
8.
Tne licensee shall comply with the Categcry A re:crendations as :specified in Table B-1 of NUREG-0578.
The Ccmmission has additional concerns, which, though they need not be resolved prior to resumption cf operation at Three Mile Island Unit 1, must be satisfac-torily addressed in a timely manner.
The Ccamission's Director of Nuclear React:
Regulation (NRR) has recommended that the following acti:ns (the "lenc-term a::icns")
e re:uired cf the licensee to resolve :.nese ::ncerns an: permit a
- '. tin; cf reas:nable assurance of the safety of '.:.;-te Operation-These a 5 s;:-it a f af.ure ::ce and effe::s analysis c' :ne I:5 to the N:.
staf' as s::n as :ra::icable;
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'00R ORGP 2.
give continued attention to transient analysis and procedures for canagement of small breaks by a formal program set up to assure timely action of these matters; 3.
ccc. ply with the Category B recommendations as specified in Table 5-1 of f;'JREG-0575; and, 4
improve emergency preparedness in accordance with the following:
(a) modify emergency plans to address changing :apabilities of plant instrurentati n, (b) extend the capability to take ap;repriate emergency actions for the p ;ulatien ar und the site to a dis-tance of ten miles.
A:: rdingly, pursuant to the At mic Energy Act of 1954, as anenced, and
- r.e ::m:-ission'.s rules anc regulations in 10 CFF,, it is hereby crdered that:
(1) the licensee shall maintain D1I-l in a cold si.atdcw. ccr.dition until further order of the Ccamission which will be issued followir.g satis-
' factory completion of the required short-tem a: icns and reasenable rogress tcward satisfactory completion of those receired long-tem a::icns referred to in secti:n IV (such sh:rt-ta-a 1.d ionc-term a::icns :: be considered "re:uired" for ;u ; ses Of this clause
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'0R ARGINAl (2) the licensee shall satisfactv. 'ly complete the 1:ng rterm actions listed in Table B-1 of f:UP.EG-057? cn the schedule sc-t cut in such table and such other icng-term actions listed ab:ve cas promptly as practicable.
IV.
The Cc= mission has determined that, in light of the acncerns listed abcve, the public health, safety and interest require that the p:)rtien of the crder referred to in clause (1) of Section III shall be irredia:cely effective.
The long-term a:tions referred to in such clause shall be th:r.e 1cng-term actions listed in se: tion II as to which the :canissi:n, pri:r ts 'the date of this crder has 'ssued immediately effective Orders against Other li esnsees.
If the C::miss issues i cediately effective orders acainst other licensee 1s imp; sing requirer.ent.
with respect to other long-term a:: ions, it will, tc the e2xtent apprecriate in :-
circumstances, issue orders, effective immediately, :: Per.;uire that the licensee demonstrate reasonable progress toward c cpletien of such other actions as a ccr tion to restart.
If the Scard determines that operatier :;an be resumed upcn cer:
tion of certain specific short-;erm actions by the licensa<.e, it shall consider ;-
extent to which the licensee has demonstrated reascnable irocress toward cc: pie:-
af the long-term acticns described in this section.
If 1-t finds that the license has demonstrated reasonable prcgress, it shall reccamend reesumption of operatier u:en ccapletion of the shcrt-term actions.
If it cannot ~nake such a finding, it shall recommend that cperation be resumed at a date that -it believes apprcpriate efie: s :ne in: rtance of the a::icn ins:lved, the time lo;; because such r:;-
Ed.;; beer ~ade en t."e prescribed sche:ule an "s Over'ridi*g reed to pr:vid2
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300ROR'GNAL V.
An Atomic Safety and Licensing Scard censisting cf Ivan 'r!. Smith, Esq., Chair-man, Cr. Walter H. Jordan, Member, and Dr. Linda W. Little, " ember, is hereby established to rule on petitiens to intervene, to cendue: the hearir.; ordered herein, ar.d to render an initial decisien in acccrdanc.e with 10 C:R 2.750.
The
- ccic Safety and Licensing Ecard will issue a further erfer specifying the date and place of the hearing and any prehearing ccnferences.
The Ecard should Fr.id i s sessiens in the vicinity of the facility and it should attempt to schedule sc e of its sessions in the evening or on weekends to per-it the maximt.in pcssible s.
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The hearing w;il be conducted in acccrdance with the as:licable previsiens cf subpar G cf the Ccmmission's ?uies of Practice set fcrth in 10 CFR Part 2.
Tne crevisions of 10 C.-
2... -it:a (consciidation of. parties j, e. /::a (special prehear-n in; ccnference and order), 2.752 (prehearing conferen e 'and crder) shall a: ply :c
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.e Ccmmission's primary cc.Tmitment is to a fair and thercugh hearing and decisier s
Given this overriding it'erctive, it is the Commissien's excectation that the Ecard will cenduct the proceeding expediticusly.
The Board shcuid as early as pessible publish an apprcpriate schedule and attempt to meet it.
A tentative sc"edule ccm;csed by t"; "camission is attached fer the Ecard's pessible use, 11 neu;n t.*e Ecarc should net be ccnstrained by it. The Ecard is ir.structed :c
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P00RAROp where feasible.
It is hereby directed, pursuant t: 2.760(a), that, upcn issuance of the initial' decision (or partial initial decision) in this matter, the record ce certified to the Commiss'en itself fer final decision.
Any party may take an appeal directly with the Commission by filing exceptions to the initial decision Vor partial initial decision) in accordance'with the previsions of 10 CFR 2.762.
Cc=missien review of the initial decision will be conducted in eccordance with 10 CFR 2.770.
In the concu:: cf this proceedin; the Licensing Ecard sh:uld exercise its auth:r' to seek :: er.sure that it receives all infoma:ien re:essary a
nor: ugh inves-gaticn and resciution of the cuestions before it.
H seve:, it shc;uld use its authority under 10 CFR 2.757 to prevent any undue delay :: the prc:eeding resuiti from any cross-examination not required for the fuli and true disclosure of the facts or from etner sources tentioned in that sec:1on.
The provisions for pre-hearing discovery sat forth in 10 CFR 2.740-2.742 shall apply to this proceeding.
Furthemore, in several le:ations, inci!uding the Ccm-mission's Public Document P.ccm and the TMI Local Document Ecca in Harrisburg, the Cc=missien will maintain and continuously update a compilatica of all publicly available information en the Three Mile Island a::ident and related matters, and it will also ;ermit info mal access to NRC staff censiderati:ns of the issues involved in tnis hearin; in the manner in mich such access is penitted in sa:::
.i:t sin; Or:csedi.;s.
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P90R BRBlWL 2.740(d), the licensing board may and should, when not inconsistent with fairnes:
to all parties, limit the extent or control the secuence of disccver;r to prevent undue delay or imposition of an undue burden en any party.
The subjects to be considered at the hearing shall include:
(1)
Whether the "short term actions" recommended by the Director cf Nuclear Reactor Regulation (set forth in Section II of this Order) are necesscry and sufficient to orovide reasonable assurance
- na the Tnree "iie Islanc Unit i facility can be c:erated witne ut endangering the healtn and safety of the public, and should be rec.uired.before resunption of cperation snocid be :ermi;;ed.
(2)
Whether the "long-term actions" reccmmended by the Director cf Nuclear Reacter Regulation (se; forth in Section II cf this Orde,-)
are necessary and sufficient to provide reasonable assurance tha.:
the facility can be operated for the long term with:ut endangering sne health and safety of the public, and should be recuired of tihe licensee as seen as practicable.
As to the issue of financial qualifica:icns mentioned ab:ve, a party. wishing Oc raise this subject as a cententien must clearly indicate why the Ticcensee's finan:ial conditi:n mign: uncermine the licensee's ability :c c:erate the plan s a'e: 2 Far:ies raising tnis issue should cc s: :sf:re :ne 5;e:ia: r)rensarin;
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P00RBRGINAL
'ihile real and' substantial concern attaches to issues such as psychol:;ical distress and others arising frem the continuing i pact of aspect:s of tne Three Mile Island accident unrelated directly to expcsure to rafiation en the part of citizens living near the plant, the C0ccissi n has net c'etemined whether such issues can legally be relevant to this proceeding.
My party wishing to raise such subjects as contentions, or as aspects cf separate cc itentiens, should brief the At:mic Energy Act and National Environmental PcGicy A:t issues he believes a:propriate to the 5:ard as part of the c ntenti:n a :epttr.ce ; recess set cut in :ne 00 nission's regulaticns.
Tne 5:ard snould tnen certify sa:n issues to the Ccanission for final decisicn prior to the issuanca cf its pre-hearing c:nfe.ence order pursuant to 10 CFR 2.752(c), either witn er without its recem endatien en such issues, as it ceems appre;:riate under the circumstan:es.
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a,lso con-n the time '.he Ccanission reaches a decisien en.nese ;ssues, r sider whether it can and should grant financial assistan:e to parties seeking ::
-aise these issues in this case.
Satisfactory eccpleticn of the required actions will be deter:;ir.ed by the Direct:-
of Nuclear Reactor Regulation.
However, prior to issuing its decisien the 5ca-d shall have authority to require staff to inform it of the detailed steps staff
- elieves necessary to implement acticns the 5:ard may re utre ar<d :
a;creve er dise:;reve cf the adeptacy of such measures. With respe:: to at:y un:::pic ed
'te s One 5:a : snal; have authority similar to :-=
Or vided in i~ CFF 50.57 ::,
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1a d h N h l /{ l' Ju uk elsewhsre in this crder, restart shall not te pe.itted untii sa.isfa:::ry ccm.
pietien of all unc mpleted shert term i.ctions.
A y affir ative deteminatien by tne Director will be based u;cn his finding that the a:tiens speciff e by the 5 card, er by the Commission en review, have been taken, that the s; ecifie' inplementing precedures empicyed are appr:priate, that the ifcensee satisfies the financial qualificatien criteria impesed en an a::li: ant for an :per ating license and that there is reascnable assurance that the facili y can rafaly resu e cpera-tion.
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C:mmission's regulations, the licensee.ty ec-.en:3.:tifi ati:r.s, s uc as these recem ended abcve by the Cirector o' Nuclear Reactor. 2;ulat?-. du -in; the pendency of this proceeding at its own risk.
VI.
If the Licensing Scard shcuid issue a decisien authcrizin; resumption of cperation uper completien of certain short-ter a:tiens by the licensee and a finding that in its judgment the licensee is making reasenable progress.' ward
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?00R ORGIO.
- .e li:enses to re.ai sh.: d:vn shall re-ain ir.- ediately effective.
Any cc:icn:
rel atine :: t.e lifting c in eciate effe:tiveness must be received by the 3
a Secretary c' the cr:-issi:n w' thin iC days of iss;ance of the certifi:ation, and
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any responses to such rctions =st be re:eived by :.e Secretary 7 days later.
The C..issic sh:11 issue an order lifting i ediate effe::iver.ess if it de:e --
that the ;ublic hia't, safety er interes; no len;er -ec; ire ir ediate effe :ive.
ness.
Tne : --issi:r's di:is' r :n t.a: :ues:ica shall r:: affect its dire::
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e An crder gran'ir.g a pititicr. f:r leave 0; intervene shall be appealable to the a *.v.*.*.e.
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that interest rey be affected by the results of the proceedin;.
Tne petition should specifically explain the reasons why intervention stculd be per--i::ed wit.-
carticular reference to the following factors:
(1) the nature of P.e petitioner's right under the A cr.ic Enercy Act to be r.ade a party to the preceeding; (2) the na ure a.d exter.: of the petitier.er's prc:er:y, f5ancial, er other in eres: in the preceecing; ar.d
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the ;cssible effect of any crcer which nay be en:erec -in the creceecing c- :ne petitioner's interest.
Tre petition should identify the specific as;ect(s) c' the 34 ject ma tter of cne creceeding as.c which petitioner wishes te intervene.
';c-later thar fi# teen days prict to the first prehearing c=nference :scheduiec '-
-he proceedinc, t.e petitioner shall file a supplement to the petitic n to inter-
.ene yhich rust include a list of cententiens which are scu sht to be litigated i-
-he ratter, and the bases for each concern set fcrth tiith r easonable specificity.
- :e:itic er ' c fails to file sucn a supple en: wricr sa:-7 s fies :ner e rec. ire.
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17' P00RORSM An answer to this Crder or petition for leave te intervene should be filed with the Secretary of the Ccemission, U.S. Nuclear Regula:ory Cc=issien,1,'ashington, D.C. 20555, Attention:
Decketing and Service.'e: tion, or may be delivered to the Comissien's Public Cocument Reca,1717 H Street, N.'J., Washington, D.C. by September 4,1979.
A copy of the petition should be sent tc the D.ecutive Legal Directer, U.S. Nuclear Regulatory Ccamission, Washington, D.C. 20555 and to Mr.
Gecrge : Tr:wbridge, Shaw, Pitt an, Potts and Tro bridge, ISCO N Street, N.W.,
Kasningt:n, C.C. 20035, attorney for the licensee.
- 9y
- vestiens or recuests fer additicnal infer ation regarding the content of :nis *.'etite should be addressed to the Chief Fearing C:unsel, Office f :ne Exe:utive Legal Direct:r, U.S. ','u:iear Regulatory Ccmmission, Washingt:n, C.C. 20555.
N:ntimely filings cf petitiens for leave te intervene, a ended petitions er supcierer.tal petitions will net be entertained absent a c'etemination that the petitioner has made a substantial showing of good cause fer the g: ranting Of a later petiti:n.
That detemination will be based en a balancing of the factors specified in 10 CFR 2.714(a)(i)-(v) and 2.714(d).
VIII.
C: pies of the fellowing dccuments are available for inspection at ne Cc-ission's Public C0cument Rocm at ~ 717 H Street, N.U., Washir.gton, D..
and a e bein; :la:ed in tne C:m.ission's locai ;utli: cc:u ent rc:m at the 5:a:e
' i:-z, :' :en".sylvania, G0ve"n ent Publica ti:ns Ie::icn, Ef u:ati:n Suil d g,
el',:r an: e.a l.u: St. eets,
.a #"is t rg, Ee nr s,. ~ ania 17I 25.
~
e 4
7 s 1 1
18 '
August 1 Cor.:nission Order April 15 Ltr. Herbein to Dente,n (prior r.ctice will te given bef:re restart)
June 28 Ltr. Herbein to Denton (rodificatier.s to be co.plete:
before THI-1 restart)
June 28 'iRC Staff Peeting su=ary on TN-1 restart NUREG-057C I&E Bulletins79-05A 79-053 79-CEC For..e %r.is si:n 9
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Secre arf of ne Co. r.issi:n Ca:ed at Washing::n, D.C.
this 9th day of Aueus
. 1979.
4 k
L.
I
P.ilestone; Tine C:Esuced Total Days Into i
(Days)
Prc:ee:ing Publicatien cf Notice 0
0 (Detailed Order)
Filing of Interventien 20 20 Petitiens
. Answers to Petitions 15-35 T' ice for Amending Pe titions 25 50 and for Negotiations re Ccr.centions Time between filine Amended 15 75 Fetitions and Cententions and Special Frehearing Conference Fublicati:n cf 5:ecial Prehearing i
SO Conference Orcer (Discovery begins)
Disccvery cc pleted 6C 140 During discovery period:
-Objections to Special Prehearing Conference Orcer 10 days
-Possible further refinement of contentions 140
? rehearing Conference Prehearing Conference Order 5
145 Filing of Testimony 20 155
(, Assumes objections to prehear-
'ing Cenference Order filed simultaneously)
Begin Hearings 15 150
- lete Hearings 50 2 4;-
riling :f :rc;: sed Fin:ings a;
25; 2.0 0
- i: ; :: :re::se: rin:ings 25 35 i:.5 :r ry 5:a-:
N II IJ J