ML19250B906
| ML19250B906 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/26/1979 |
| From: | Gossick L NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | Goodling B HOUSE OF REP. |
| Shared Package | |
| ML19250B907 | List: |
| References | |
| NUDOCS 7911060066 | |
| Download: ML19250B906 (2) | |
Text
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'o, UNITED STATES y '}c, g NUCLEAR REGULATORY COMMISSION
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jrz 9 E WASHINGTON, D. C. 20555
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SEP 2 61979 The Honorable Bill Goodling United States House of Representatives Washington, D.C.
20515
Dear Congressman Goodling:
. This letter is in response to your letter to Chairman Hendrie dated July 31, 1979 wherein you. stated your concern about NRC plans for reopening Three Mile Island, Unit 1 (TMI-1).
Chairman Hendrie ha:, asked me to respond to your letter in view of the fact that there are now adjudicatory proceedings for Three Mile Island, Unit 1 under-way before an Atomic Safety and Licensing Board. Under the Nuclear Regulatory Cormiission (NRC) rules of practice, Ch:irman Hendrie and the members of the Commission will be called upon to review the Orders and decision of the Licen-sing Board and hence, it would be inappropriate for him or other members of the Commission to comment on the matters raised in your letter.
On July 2,1979, the~~Cormiission ordered that TM'-
remain in a cold shutdown condition until further order by the Commission itself and stated that a public hearing would be held prior to restart of TMI-1.
The CorTaission believes that public participation is a vital ingredient decling with those matters related to the TMI-l restart.
On August 9,1979, the Commission issued an additional Order on TMI-l specifying the basis for the Shutdown Order and the procedures to govern the hearings regard-ing any TMI-l restart. On the basis of this hearing, the Commission will deter-mine whether any further operation of TMI-l will be permitted, and if so, under what conditions.
I have enclosed a copy of the August 9,1979 Order for your information.
As a result of the TMI accident, the NRC required all nuclear power plants which utilize a Babcock & Wilcox (B&W)-designed pressurized water reactor similar to TMI 1/2 to take specific actions prior to these units going back on line.
In addition to the actions required on the other B&W units, additional actions were specified in the August 9,1979 Order for TMI-1, such as potential interactions between TMI-l and the damaged TMI-2 and recognized deficiencies in emergency plans and station operating procedures. Also, specific actions are required for TMI-l as required for all other operating nuclear power plants, based on the NRC's lessons learned from the TMI accident.
R77 044 4 7911060O LL
e The Honorable Bill Goodling The Commission carefully considered the time required for completing all tasks related to the Order on TM:-l and which mes be completed prior to any restart of TMI-1. A Conmission schedule calling for / editious handling of the necessary NRC staff actions and procedural actions ra csired for the hearing process is pro-vided on the last page of the Cormission's Order. Based on that schedule, I do not believe that the restart of TMI-l could occur before Septei.iber,1980.
I trust this response addressed the concern raised in your letter.
In the meantime, if you have any further comments, please feel free to direct them to R. H. Vollmer (telephone 301/492-7347) within the Conmission's Office of Nuclear Reactor Regulation.
~
Si ncerely,
' Original signed by R. G. Smith Lee V. Gossick Executive Director for Operations Enclosure :
As stated 1?77 045
UNITED. STATES 0F AMERICA NUCLEAR REGULATORY C0"JilSSION COMMISSIONERS:
Joseph M. Hendrie, Chaiman Victor Gilinsky Richard T. Kennedy Peter A. Bradford John F. Ahearne
)
In the Matter of
)
)
METROPOLITAN EDISON COMPANY Docket.to. 50-289 (Three Mile Island Nuclear Station,
)
Unit No. 1)
)
ORDER AND NOTICE OF HEARING I.
The Metropolitan Edison Company (the licensee) is holder of Facillity Operatir License No. DPR-50 which authorizes the operation of tSe muclear povier reactor known as Three Mile Island Nuclear Station, Unit No.1 (Oe facility or TMI-1), 2 steady state power levels not in excess of 2535 megawatts thermal (rated power).
The facility is a Babco.:k and Wilcox (B&W) designed press:urized water reactor
^(PWR) located at the licensee's site ten miles southeast of Harrisburg, Pennsyl-D*
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1 II.
On July 2,1979, the Commission ordered that the facility remain in a cold shutdown condition until further order of the Com:.ission.and stated that a heari-will be conducted prior to any restart of the facility.
On the basis of that hearing the Commission will detemine whether any further cperation will be per-mitted and, if so, under what conditions.
The C0=issic, herein specifies the basis for its concerns and the procedures to goverr further proceedings in this mattir.
For the reasons later set forth, the Ccrission has detemined that 1777 046 bul' q g 00 F/ 055(o
2' satisfactory completion of certain short-term actions and resciution of various 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 detemined that certain additional long-tem actions are, for the reasons given below, required to be completed cs prcmptly as practicable, and that reasonable 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 of hearing further establishes procedures for a hearing and decision on the : articular issues identified in Section V of this Order.
Tne 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 action,s rec; ired prior to restart of the facility must be completed prior to any Cc..ission Order lifting the suspension of operation.
D D
Accordingly, the Atomic Safety and Licensing Board designated to conduct this pro-ceeding should give priority to consideration of those issues which are related directly to ' suspension of operation.
To the extent feasible, the Board should defer full review of the issues related to the longer-tem actions until after th:
rendering of a partial initial decision regarding the suscension-related issues.
The Commission's July 2,1979 Order recited that "the C:r.-ission presently lacks tr.e recuisite reasonable assurance that the... Li:5 see's Three Mile Island Unit No.1 Facility... car be operated without er.:a ;5rir; the health and sa; of th public."
The bases for that conclusion (wnic re. air.s valid) are:
1777 047
3, In the course of its evaluation to date of the accident at the Three Mile Island Unit No. 2 facility, which utilizes a B&U designed PWR, the Nuclear F.egt ' dtory Commission staff has ascertained that P&W designed reactors appear to be unusual' sensitive to certain off-nomal transient conditions cricinating in the secondar;-
hystem.
'he features of the B&W design that contributa to this sensitivity are:
(1) design of the steam generators to operate with relatively small liquid volur.e in the secondary side; (2) the lack of direct initi.ation of reactor trip upon thc occurrence of off-normal conditions in the feedwater system; (3) reliance on an integrated control system (ICS) to automatically regulate feedwater flow; (4) actuation before reactor trip of a pilot-operated relief valve on the primar, system pressurize > (which, if the valve sticks open, can aggravate the event);
and (5) a low steam generator elevation (relative to the reacter vessel) which provides a smaller driving head for natural circulation.
Because of these features, B&W designed reactors place core ruliance on the reliabi_lity and performance characteristics of the auxiliary -feedwater system, ::
integrated control system, and the emergency core cooling sys-tem (ECCS) performa-to recover from frequent anticipated transients, such as loss of offsite power a-1.oss of normal feedwater, than do other PWR designs.
Tnis, in turn, places a ic Surden on the plant operators in the event of off-nomal system behavior during 3r fD 'n a
anticipated transients.
D D
aw As a result of a preliminary review of the Three Mile Islar.d Unit Nc. 2 accicer-chronolocy, the NRC staff initially identified several hu an errors that occurr-curinc the accident and contcibuted significantly to i s severity.
All holders cperatinc licer.ses, except. Metropolitan Edison, wacse piar.ts were already shut-coun, viere subsecuently instructed to take a number of ir.me:'-iate actions to avc M77 048
4s repetition of errors, in accordance with bulletins issued by the Cor.nissior.'s Office of Inspection and Enforcement (IE).
In additien, tne NRC staff began an immediate reevaluation of the design features of B&W reacto rs to detemine whether additional safety corrections or improvements were necessa:y with respect to these r.eactors.
This evaluation involved numerous r.eetings with.E&W and certain of the affected licensees.
The evaluation identified design features as discussed above which indicated that S&W designed reactors are unusually sensitive to cer:riin off-nortal transient conditions originating in the seconc'ary system.
As a result, an additional bulletin was issued by IE which instructed holders of operating licenses for B&W designed reactors to take further actions. including immediate changes to decrease the reactor high pressure trip point and increase the pressurizer pilot-operated relief valve setting.
Also, as a result of this evaluation, the NRC staff identified certain other safety cwncerns that warrantec additional short-term design and procedural changes at oper ating facilities havin; B&W designed reactors.
These were identified as items (a) -through (e) on page 1 ~
of the Office of Nuclear Reactor Regulation Status Report to the Commission of April 25,1979.
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In addition to the items identified for the other B&W reactors, the unique circur-stances at TMI require that additional safety con: erns identified by the NRC staf be resolved prior to restart.
Tnese concerns resait frca fi) potential inter-action between Unit 1 and the damaged Unit 2, (2; c;esticns about the managemen:
ca: abilities and technical resources of Metrc:cli an Edis: ;, including the
'r act of the Unit 2 acticent on these, (3) P.e :::er.tial effect cf operations M77 049
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necessary to decontaminate the Unit 2 facility on Unit 1, and (4) recognized deficiencies in emergency plans and station operating procedures.
Based on the ebove, the Commission's Director of fluclear Reactor Regulation (NRR) has recom-mended that the following actions (the "short-term actions") be required of the licensee to resolve the concerns stated herein and pemit a finding of reasonable assurance that the facility can safely resume operation.
1.
Tne licensee shall take the following actions with respect to TMI-1:
(a)
Upgrade the timeliness and reliability of the E.msrcency Feedwater (ER.')
system by perfoming the itens specified in Enclcsure 1 of the licensee's June 28,1979 letter.
Changes in design will be sub-itted to the fiRC staff for review.
(b)
Develop and implement operating procedures for initiatinc and controlling ER.' independent of Integrated Control System (ICS) centrol.
(c)
Insta.ll a hard-wired control grade reactor trip on loss of rnain feedwater and/or on turbine trip.
(d)
Complete analyses for potential small breaks and develop and implement operating instructions to define operator action.
('e). Augment the retraining of all Reactor Operators and Senior Reactor Operators assigned to the control room including training in the areas of natural circulation and small break loss of ccolant accidents includ-ing revised procedures and the THI-2 accident.
All cperators Will also receive training at the B&W simulator on the W.:-2 accident and the licensee will conduct a 100 percent reexaminati:- c' all operators i n tnese areas.
tiRC will administer complete exa-i a-i:ns to all licensed
' ersonnel in accordance with 10 CFR 55.2C-22..
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6 2.
Tne licensee shall provide for t!RC review and approval of all applicable actic-specified in IE Bulletins79-05A, 79-058, and 79-05C.
3.
The ' licensee shall improve his emergency preparedness in accordance with the following:
(a)
Upgrade emergency plans to satisfy Regulatory Guide 7.101 with special attention to action level criteria based on plant pa: ameters.
(b)
Establish an Energency Operations Center for Federal, State anci Local
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Officials and designate a location and an alternate Toca: ion anci pro-vide communications to plant.
(c) Upgrade offsite mcnitoring capability, including additional theamo-luminescent dosimeters or equivalent.
(d) Assess the relationship of State / Local plans to the licensee pMans so as to assure the capability to take emergency actions.
(e)
Conduct a test exercise of its emergency plan.
'4.
The licensee shall demonstrate that decontamination arc 3r restoration o.perations at TMI-2 will not affect safe operations at TMI-1.
The ' licensee shall provide separation and/or isolation of TMI 1/2 radioactive licluid transfer lines, fuel handling areas, ventilation systems, and sampling lines..
Effluent monitoring instruments shall have the capability of ciscriminating between effluents resuiting frca Unit 1 or Unit 2 operations.
5.
Tr.e licensee shall demonstrate that the waste arager.ent capability, inclue-s.crage and processing, for solid, licuid, and gasec.s wastes is adecuate to n77 051 D *
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7 s assure safe operation of TMI-1, and that TM4-1 waste handling capability is not relied on by operations at THI-2.
6.
The licensee shall demonstrate his managerial' capability and resources to operate Unit 1 while maintaining Unit 2 in a safe configuration and carrying out planned decontamination and/or restoration activities.
Issues to be addressed include the adequacy of groups providing safety review and operational advice, the management and technical capability and training of operctions staff, the adequacy of the operational Quality Assurance program and the facility procedurer and the capability of important support organizations such as Health Physics and Plant Maintenance.
7.
The licensee shall demonstrate his financial qualifications to thee extent relevant to his ability to operate TMI-1 safely.
9 8.
The licensee shall comply with the Category A reco:r.mendations as !specified in Table B-1 of NUREG-0578.
The Commission has additional concerns, which, though they need not be resolved prior to resumption of operation at Three Mile Island Unit 1, must be satisfac-
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torily addressed in a timely manner.
The Commission's Director of Nuclear React:
Regulation (NRR) has recommended that the following actions (the "long-tera actions") be required of the licensee to resolve these concerns and pent,it a fir. ding of reasonable assurance of the safety of long-tem cperation-These are submit a failure mode and effects analysis cf r.e I.5 tc the NRC
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staff as soon as practicable; o mam my n n3 p77 052 mMJL%
8 2.
give continued attention to transient analysis ar.J procedures for management of small breaks by a femal program set up to assure timely action of t%se matters; 3.
comply with the Category B recommendations as specified in Table B-1 of l;'JREG-0578; and, 4.
improve emergency preparedness in accordance with the following:
(a) modify emergency plans to address changing capabilities of plant instrumentation, (b) extend the capability to take appropriate e ercency actions for the population around the site to a dis-tance of ten miles.
II!.
Accordingly, pursuant to the Atomic Energy Act of 1954, as anended, and the Ccamission's rules and regulations in 10 CFR, it is hereby ordered that:
(1) the licensee shall maintain 1NI-l in a cold shutdown condition until further order of the Commission which will be issued following satis-
- factory completion of the required short-tena actions and reasonable progress toward satisfactory completion of those recuired long-term actions referred to in section IV (such short-tenn and long-term actions to be consicered " required" for pur;cses cf this clause v.hich are detemined by the Commission, after review of the Licensing i:ard's cecision, c be necessary and suffi:ier: :: :rcvide adecuate
- rstection cf the public health and safety); ar:
1777.053 D**D
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9 (2) the licensee shall satisfactorily complete.the 1:ng tem actions listed in Table B-1 of NUP,EG-057F on the schedule set out in such table and such other long-tem actions listed absve tas ;romptly as practicable.
IV.
The Commission has detemined that, in light of the econcerns listed above, the public health, safety and interest require that the p:)rtion of the order referred to in clause (1) of Section III shc11 be im ediw.ely effective.
The long-tem actions referred to in such clause shall be ther.e long-tem actions listed in section II as to which the Comr.ission, pri:r to the date of this order has issued immediately effective orders against other licesnsees.
If the Commiss issues immediately effective orders against other license 2-ts imposing requirement:
w'ith respect to other long-tem actions, it will, to the e2xtent appropriate in t-circumstances, issue orders, effective im ediately, to fer.;uire that the licensee demonstrate reasonable progress toward completion of such other actions as a con:
tion to restart.
If the Board detemines that operation :.;an be resumed upon cc:
tion of certain specific short-tem actions by the license.e, it shall consider t-extent to %ich the licensee has demonstrated reasonable progress toward completi o.f the long-tem actions described in this section.
If hf, finds that the license-has ' demonstrated reasonable progress, it shall recommend resumption of operation upon completion of the short-tem actions.
If it cannot make such a finding, it shall reccmmend that operation be resumec at a date that it believes appropriatt
-eflects the importance of the action involved, the time '. c s : be:ause such progr "ad not been made on the prescribed schedule and t e Over-id'n; r. sed to provide h
a:ecuate prctection for the public healtr anc sa#ety.
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10, V.
An Atomic Safety and Licensing Board consistino of Ivan 'r!. Smith, Esq., Chair-man, Dr. Walter H. Jordan, Member, and Dr. Linda W. Little, Member, is hereby established to rule on petitions to interene, to concuct the hearing ordered herein, and to render an initial decision in accordance with 10 CFR 2.760.
The Atomic Safety and Licensing Board will issue a further order specifying the date and place of the nearing and any arehearing conferences.
Tne Ecard should hold its sessions in the vicinity of the facility and it shculd attempt to schedule some of its sessions in the evening or on weekends to permit the maximum possible public attendance.
The hearing will be conducted in accordance with the applicable provisions of subpart G of the Commission's Rules of Practice set fcrth in 10 CFR Part 2.
The provisions of 10 CFR 2.715a (consolidation of parties), 2.751a (special prehear-ing conference and order), 2.752 (prehearing conference and order) shall apply to this proceeding.
The Commission's primary commitment is to a fair and therough hearing and decisior Given this overriding imperative, it is the Commission's expectation that the Board will conduct the proceeding expeditiously, lhe Board should as early as possible publish an appropriate schedule and attempt to meet it.
A tentative schedule composed by the Commission is attached for the Beard's possible use, although the Board should not be constrained by it. The 5:ard is instructed to explore opportunities to shorten the time limits prc< iced ir. :he F.Jies pursuant
The Licensing Scard is hereby irs r.::e: to :cnsolidate
- articitation of carties pors.uant to 10 CFR 2.715a r.e.ixi.um extent prac-
.i:able censister.: with the provisions of that re;ula-i:n.
It its review of the
- .itial Decision, the Co mission will invoke 10 CFR 2.711 c shcr:en time limits p77.055
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where feasible.
It is hereby directed, pursuant.to 2.760(a), that, upon issuarce of the initial decision (or partial initial decision) in this matter, the record be certified to the Commission itself for final decision.
- ny party may take an appeal directly with the Commission by filing excepuons to the initial decision
'(or partial initial decision) in accordance with the previsicns of 10 CFR 2.762.
Commission review of the initial decision will be conducted in accordance with 10 CFR 2.770.
In the conduct of this proceeding the Licensing Scard shcald exercise its authori to seek to ensure that it receives all information ne:estary to a thorough inves; gation and resolution of the questions before it.
Ho./ever, it should use its authority under 10 CFR 2.757 to prevent
'.r.r. undue delay to the proceeding resulti from any cross-examination not required for the full and true disc.losure of the facts or from other sources nentioned in that section.
The provisions for pre-hearing discovery set forth in 10 CFR 2.740-2.742 shall apply to this proceeding.
Furthermore, in several ic:ations, inci!uding the Com-mission's Public Document P.com and the TMI Local Document Room in Harrisburg, the Commission will maintain and continuously update a compilation of 611 publicly avaikable informa:lon on the Three Mile Island accident and related matters, and it will also permit informal access to NRC staff considerati ns of the issues involved in this hearing in the manner in which such access is permitted in reactor licensing proceedings.
It shall be an a:ec.ite as;;nse to any dis-covery recuest to state that the information or :::.; r: re:;ested is available ir the public ccmpilation and. :o provide sufficie.; 'r.fc-rition to locate the
- ccu ent or infer ation.
Moreover, as prcvided by 1: C R 2.7C. ) and 10 CFR Y
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12' 2.740(d), the licensing board may and should, when not inconsistent with fairness to all parties, limit the extent or control the sequence of discover.y 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 Reactor Regulation (set forth in Section II of this Ordt.:r) are recessary and sufficient to provide reasonable assurance that the Three Mile Island Unit 1 facility can be cperated witno.trt endangering the health and safety of the public, and should be required before resunption of operation should be :ermitted.
(2) Whether the "long-term actions" reccamended by tr.e Director of Nuclear Reactor Regulation (set forth in Section II of this Orde,-)
are necessary and sufficient to provide reasonable assurance thE.t the facility can be operated for the long term without endangering the health and safety of the public, and should be recuired of tPie licensee as soon as practicable.
As to the issue of financial qualifications mentioned above, a party :. wishing to raise this subject as a contention must clearly incicate why the licenisee's financial condition might undermine the licensee's ability to cperate the plant s a fely.
Parties raising this issue should do so bef:re ne Special Prehearing
- -reren:e.
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13' While real and substantial concern attaches to issues such as ps;ychological distress and others arising from the continuing impact of aspects of the Three Mile Island accident unrelated directly to exposure to aciittion on the part of citizens living near the plant, the Ccamission has not cietermined whether such issues can legally be relevant to this proceeding.
Iny party wishing to raise such subjects as contentions, or as aspects of separate cor.tentions, should brief the Atomic Energy Act and National Environmer.tal Pcilicy Act issues he believes appropriate to the Board as part of the conter,tien acceptance process set cut in the Conmission's regulations.
The Board should then certify such issues to the Comnission for final decision prior to the issuance of its pre-hearing conference order pursuant to 10 CFR 2.752(c), either wit.n er without its reccanendation en such issues, as it deems appropriate under the circumstances.
At the time the Commission reaches a decision on these issues, it will also con-sider whether it can and should grant financial assistance to parties seeking to raise these issues in this case.
Satisfactory completion of the required actions will be determined by the Director of Nuclear Reactor Regulation.
However, prior to issuing its decision the Board shall have authority to require staff to inform it of the detailed steps staff believes necessary to implement actions the Board may recuire arid to approve or disa prove of the adequacy of such measures.
Witn respec: to any uncompleted i ters :he Board shall have authority similar to :na: orovided in 10 CFR 50.57(b)
- take such acticns or to inpose such limitatic s or cc.fi.icns as it believes ne:essary :c crc:ect the publ.ic health and safe ;. -
- revi:ec, that, as provided f
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elsewhere in this order, restart shall not be per.itted until satisfactory com-pletion of all uncompleted short-ten, actions.
ky affin ative detemination by the Director will be based upon his finding that the actions specified by the Scard, or by the Commission on review, have been :aken, that the specified implementing procedures employed are appropriate, that the licensee satisfies the financial cualification criteria imposed on an apolicant for an oper ating license.
and that there is reasonable assurance that the facility can safely resune opera-tion.
As noted above, the Atomic Safety and Licensing isard should a: cord priority to the consideration of matters relating to the nee: for continued sust ension of operating authority.
Uithin the limitations of 10 CFR 50.59 a7c 2.717'b' of the Commission's regulations, the licensee may commer.:e n:dificati
.s, s ucP as those recommended above by the Director of Nuclear Reactor RegulatW., cur-in; the pendency of this proceeding at its own risk.
VI.
If the Licensing Board should issue a decision authorizing resumption of operation upon completion of certain short-tena actions by the licensee and a finding that in its judgment the licensee is making reasonable progress toward completion of the long-term actions specified in this order as to tr.hich the Coc-mission has issued immediately effective orders a; air.st othe-licensees, and subsequently if staff certifies that those shcr:- er-acticns. ave beer complete
- its satisfaction, the Ccamissicr. will issue E-
- r:e
<ith' i c'ays after such certification cecicing whether the :rtvisic
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s 15 the licenses to recair. sh:t d:wn shall remain ir.nediately effective.
Any raotior.:
relating to the lifting of in eciate effectiveness nust be received by the Secretary o' the Corrissi:n w'thir 1C days of issuance of the certification, and any responses tc such motions must be received by the Secretary 7 days later.
The Conmissior. shall issue an order lifting inmediate effectiveness if it deter-that the public healtS, stfety or interes; no longer receire immediate effective-ness.
Tne Cogi ssion's de:i s'or on t.a: uestion shall not affect its direct appellate rev'e.: Of t.e carits cf t'e E ard's decisicn.
By Se:tembe
',1_7., t' e licenses r.ay file a viten answer to this Order VII.
and ar.y persor whose inte est may be affected by this arc:eeding may file a written pet't'or o ir.tervere.
Pet't'or.s for lea.e to ir.:ervene cust be filed ir. accordan:e wit-the : omission's "?.ules of Pra:tice' fer D:nestic Licensing Proceedin;s' in 1: CF:
'a-t 2.
I' a :etition for leave to intervene is filed by the above date, the A o-i; Sa#ety and Licensing Ecard established by this Order will rule o
-he :e i-icn ard issue a aperopriate fur:.her order.
An order wholly deryin; a :e:i:icn fcr leave t: in:ervene shall be appealable by the petitioner 0 the Com-iss'.or. 'tself w' thin ten days after service of the order.
An order grantir.g a pet tior. for leave to intervene shall be appealable to the Ccamission itself by a, arty cther thin the petitioner on the cuestion of whetF:
the petitior. shca:c have teen wr.o:ly der.ied.
Is re:;i e: b 1 C F F. 2. 7' ', t ;e-iti:. #:r leave :: #. e vene 5.all set fortr
.-i :: :a r t i : '. i r ' :;. :P.s '.:e :es: c' :he :e:i:icr.er i- :ne :r::ee:ir.:, and how I
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16' that interest may be affected by the results of the proceeding.
The petition should specifically explain the reasons why intervention s50uid be pemitted with particular reference to the following factors:
(1) the nature of the petitioner's right under the A:cmic Energy Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's preser:y, 'i.nancial, cr other interest in the proceeding; and
'2) the possible effect of any order which may be enteret -in the proceecing on the petitioner's interest.
The petition shou'.d identify the specific aspect (s) c' the subject ma tter of the aroceeding as to which petitioner wishes to intervene.
ot later thar. fi# teen days prior to the first prehearing c:anference : scheduled ir the proceedinc, the petitioner shall file a supplement to the petitio n to inter-vene,which must include a list of contentions which are sou ght to be litigated in the natter, 'and the bases for each concern set forth with r easonable specificity.
cetitioner w5o fails to file such a supplement which sat 9 sfies thes e require-ents with res ect to at least one contention will n:: be ;ermitted no participa-as a ;tr:y.
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it An answer to this Order or petition for leave to intervene should be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Co=issicn, Washington,
.D.C. 20555, Attention:
Docketing and Service Section, cr may be celivered to th+
Commission's Public Document Room,1717 H Street, N.M., Washington, D.C. by September 4,1979.
A copy of the petition should be sent to the Executive Legal Director, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 and to Mr.
George F. Trowbridge, Shaw, Pittman, Potts and Trowbridge,1800 M Street, N.W.,
Washingttn, D.C. 20036, attorney for the licensee.
My cuestions or reauests for adcitional infoma tion regarding the content of t.is '.'otice should be addressed to the Chief Hearing Counsel, Office of the Exe:utive i.egal Director, U.S. 'bciear Regulatory Commission, Washington, D.C. 20555.
Nontimely filings of petitions for leave to intervene, arended petitions or supolemental petitions will not be entertained absent a cereminetion that the petitioner has made a substantial showing of good cause for the granting of a later petition.
That detemination will be based on a balancing of the factors specified in 10 CFR 2.714(a)(i)-(v) and 2.714(d).
VIII.
Copies of the following documents are available for inspection at the Commission's Public Document Room at 1717 H Street, N.U., Hashington, D.C.
and are being placed in the Commission's local ;.$'.i: de:;rer.t rc;m at the Stat:
Library of Pennsylvania, Government Publications Se::icn, Educaticn Suilding,
- vealth and Walnut Streets, Harrisburg, Per-s,.~ aria ' 7:26.
s W
O 1??7 062
18 '
August 1 Commission Order April 15 Ltr. Herbein to Denten (prior r.otice will be given before restart)
June 28 Ltr. Herbein to Denton (nodificatier.s to be coa.pleted
.re Tlil-1 restart)
June 28 IDC Staff Meeting summary on TIG-1 restart flUREG-0578 I&E Bulletins79-05A 79-05B 79-05C For the Srr.ission l1 l
t h%
/
5.Q'LEL,J. Ch:Ls Secretary of the Cor. mission i
Da ted a t 'r.'a s hi ng ton, D. C.
this 9th day of Auoust_
. 1979.
P77 063
Milestone Tine Cc$suned Total Days Into (Days)
Preceecing Publication of !!otice 0
0 (Detailed Order)
Filing of Intervention 20 20 Petitions Answers to Petitions 15 35 Time fcr Amending Petitions 25 50 and for liegotiations re Contentions Time betvieen filino Amended 15 75 Fetitions and Contentions and Special Prehearing Conference Fublication of Special Prehearing E
S0 Conference Order (Discovery begins)
Discovery completed 60 140 During discovery period:
-Objections to Special Prehearing Conference Order 10 days
-Possible further refinement of contentions 140 Prehearing Conference Prehearing Conference Order 5
145 20 155 Filing of Testimony (Assumes _ objections to prehear-
'ing Conference Order filed simultaneously)
Begin Hearings 15 180 Complete Hearings 60 240 riiir.g of Proposec Fincings 40 250
- ecl;. co Preccsed Findir.gs iC 290 E
335
- ecisicr. cy Ecard D " " l0
" l0
' T ] T\\
p77,064 ooM eM M ML