ML19207B756
| ML19207B756 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/31/1979 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Gilinsky V, Hendrie J, Kennedy R NRC COMMISSION (OCM) |
| References | |
| NUDOCS 7909050219 | |
| Download: ML19207B756 (13) | |
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C;cnissioner Ahe rne I.
Harold R. Canton, Dirsctoc FRC i:
Offica of ::uclear Racctor Ragulation
-(Shme:S T. A Rehm Lee V. Gossick THRU :
' Executive Director for Cparaticas
, STAFF VIEliS OF TEC'd?lICAL ARDS OF CO':CEPJ! TO E C^
t III CCM ISSIO:i'S FURTHER ORDER I:! Y:iE THREE MIL l
'SUGJECT:
U:!IT 1 SUSPEriSICil i,
On duly 2,1979, the Corm:ission ordered that the. Three dile Island Unit 1 h
reactor remain in cold shutdo:!n candition until ^trchac crder of J
Tha Cedar also provided that t' > Cec ;ission 9; auld i suo a mission itself.
furcher or. ice within.hirty days specifying in - Mil de has :s for:issice direct?.d is cen-e inich :.:.2 Cc:
l carr.s, c.nd the peccaduccs to gevara the i.uri:g.s ashed to crovida listing
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I be held pricr to restart of th.. facility.
of the areas of technical concern to ce rasolvad in c:nnection with any re-l start of Three Mile Igiand Unit 1.
l Th2 Office of the E: ccutive LaCal Director 'ns etTraady prnvid:d v;o C=issica
'la uith a draft of the procedural pertiens of M:a Cm:iscicn's ?ur.':ar ordee.
have retyped that draft (except for Section IV which is purely. recedural),
o The inta-inscrting ".'at we believe to be the approprinta technical content.'la a l
F: tad d. aft is,att:ched.
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Offica o? "; clear Reacter ?.e:uirtica t
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', Docket No. 50-346 Metropolitan Edison Company, Three Mile Island Nuclear Station, Unit No.1 ORDER AND NOTICE OF HEARING The Metropolitan Edison Company (the licensee) is holder of Facility Operating I.
License No. DRR-50 which authorizes the operation of"the nuclear power reactor i
Unit No. 1 (the facility or TMI-1),
_ __yhown as Three Mile Island. Nuclear Stat on, at steady state pcwer levels not in excess of 2535 megawatts thermai (rated The facility is a Babcock and Wilcox (S&W) designed pressuri:ed water power).
reactor (PWR) located at the licensee's site ten miles sottheast of Harrisburg, Pennsylvania.
On July 2,1979, the Commission ordered that the ' :ility.emain in a cold II.
shutdown condition until further order of the Commissic, and stated that a hearing of the facility. The Commission herein will be conducted prior to any restar:
the basis for its can'cerns and the precedures to govern
' specifies For the reasons later set forth, the Com-further proceedings in this matter.
mission has determined that satisfactory ccmpletien of cercain actions and resol of.various concerns described herein are require: to provide reasonable assurance that the facility can be operate.d without endangering the health and safety of The Commission has determined that certair additional long-term the public.
actions are, for the reasons given below, required to be ccmpleted as promptly as practicable in order to provide reasonable assurance that the facility can This Order 2nd notice of earin3 furtner be operated safely over the long term.
establishes procedures for a hearing and decision on the particular issuer oi 2os r2A,k &q/'
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.v identified in Section IV of this Order.
The Connission has determined that hearing and decision (with review thereof) on the issues relating to the actions required prior to restart of the facility must ce completed prior to any Com-mission Order lifting the suspension of operation.
Accordingly, the Atomic Safety and Licensing Board designated to conduct this proceeding should give priority co consideration of those issues which are related directly to suspension of operation. To the extent feasible, the Board should defer en the issues related to the longer-term actions n til after the rencering of a partial initial decision regarding the suspension-related issues.
The Ccmmission's July 2,'1979 Crd:
recited that "the Commission presently lacks the requisite reasonable as ;rance that the... Licensee's Three Mile Island Unit No.1 Facility... :an be operated withcut endancaring the health and safety of the public." The bases for that conclusion (which remains valid) are:
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In the course of its evaluation to date of the accident a. the nree 73.11e Island Unit No. 2 facility, which u.ill:es a 3rM d* gned M, the f
Nuclear regu.la:::y Cxmissica st.aff has escertained e.at Esw desig.W raa: tors e; gear to be unusually sensitive to certain eff-r. :.11 :::n:1cn:
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. condition.: crigir,-ting !.n the r-erendary cys:c.,..
Qe f az ures of :he
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2C.i deic;n th:t centribusq to this etnaitivity :re:
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0 cign of ::,2 1
j;t.22n c.nerat:rs to ::erztc with relati.valy :: all lic/id voirr: in
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ste:-dary ?ide; (2) tne leek of dirce initiati,n :: :ac :Or tric up:n
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the Occ.:.r r en ce c f c ff -no m.a1 ::,-d i t. : n3 in *.24 f er : 4: sys.:.; (2) re--
I lian.:e en an integrated cent:01 ryste:- GCS) t: : =
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. feedaater flow; (4) actuatica b-efore reactor trip of a pilot-cparated relief velve en th prir.ury syster. pressurl:er D.'. ic., if ita valvr.
Othhs opin, can Egyrovate the event); trd (5) a low stes.a generator elevation (relative to the reacter vessel) shich pro.-idas a s: alle:
drivirg head for natural circulation.
e Because of these featv.res, MW dstigned rasetors place =cre reliance an the reliability and performance characteristics of t.5.e Ju.:4111ery fr.ed-water systc=:, the integrated centrol systen., and the c:targerc/ ccre coel--
e ing syste:: (r%S) porfor=.1:rce to recover fr= f repen z:iticipated transients, such as icss of offsite p:wsr ar>d less of norm.1 feef ter, than do other t'ri?. designs.
This, in turn, places a large burien en the in the cvent of off-ncr:ul systes behavier da:1 c such plant opar: tor:
anticipated "ransients.
As a result of a preliminary review of the Three Mile Island Unit No. 2 accicant caronoicgy, the NRC staff initially identified several human errors that occurred during the accident and contributed significantly to its severity. All holders of operating licenses, except Metropolitan Edison, whcsa plants were already shutdown, were subsequently instructed to take a nuccer of immediate actions to avoid repetition of errors, in accordance with bulletins issued by the Ccmmission's Office of Inspection and Enforcement (IE).
In addition, the NRC staff began an immediate reevaluation of the design features of B&W reactors to detemi te whether additional safety corrections or improvements were necessary with respect This evaluation involved numerous meetings with B&W to these rea:cors.
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E and certain,f the affected licensees.
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. 'Ibe~ evaluatica identified design features e$ ~ discussed cbove which indi-
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cr.ted that E&W designed reactors are unusu.nlly sensitive to cerrain off-nor:r.11 transient conditiens originating in the st.condary system.
As a result, an additional bulletin was issued by II which instru:ced holdera r
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of op3reting licensas for B&W designed res= tors to tzha further actien=,
inclu: ling 1.1.ncdicto chingss to decrease the reactor high pressure t. rip point arxi in:resse the pressuri er pilot-operated reliGf valve set-ting.
Also, as a result of this evaluation, the IGC staff icbatificd cort. sin
- - - - - other safety concerns that wccrented additional short arm design' en !
proc 0 dural changes at operating facilitics h*.ving B&W designed ruactors.
Idess were identified as item.s (a) through (e) on page.1-7 of the office
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of N:.: clear Reactor Regulation Statt.::s Rep rt to the Crnission of April 25, 1979 In addition to the items identified for the other B&W reactors, the unique circumstances at TMI require that additional safety concerns identified by the NRC staff be resolved. These concerns result from (1) potential inter-action between Unit 1 and the damaged Unit 2, (2) the impact of the Unit 2 accident on the management and technical resources of Metropclitan Edison, (3) the operations necessary to decontaminate the Unit 2 facility, and (a) recognized deficiencies in emergency plans and station operating procedures.
Assurance must be provided that these items,1-4, which could have an impact on the safety of operating Unit 1 in addition to the technical features already identified for the other S&W plants, be resolved prior to restart.
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Based on the above, the Commission's Director of Nuclear Reactor Regulation-(NRR) has recommended that the following actions (the "short-tem 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.
The licensee shall take the following actions with respect to TMI-1:
(a) Upgrade the' timeliness and reliability of the Emergency Feedwater_
(EFW) system by performing the items specified in Enclosure 1 of the licensees June 23, 1979 letter. Changes in design will be submitted to the NRC staff for review.
(b)
Develop and implement operating procedures for initiating and controlling EF4 indepe, dent of Integrated Control System (ICS) control.
(c)
Install a hard-wired control grade reactor trip on loss of main 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 Cperators and Senior Reactor dperators assigned to the control roca including training in the areas of natural circulation and small break loss of coolant accidents includ-ing revised procedures and the TMI-2 accident. All operators will also receive training at the EsW simulator on the TMI-2 accident and the licensee will conduct a 100 percent reexamination of all operators in
'iRC will administer com;lete examinations to all licensed these areas.
personnel.
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The '1censee shall provide for NRC review and approval all applicable actions specified in IE Bulletins79-05A and 79-058.
3.
The licensee shall improve his emargency preparedness in accordance with the following:
(a) Upgrade emergency plans to satisfy Regulatory Guide 1.101 with special attention to action level criteria based on plant parameters.
(b)
Establish an Emergency Operations Center for Federal, State and Local Officials and designate a location and an alternate location and provide communications to plant.
(c)
Upgrade offsite monitoring capability, including additional thermo-luminescent dosimeters or equivalent.
(d) Assess the relationship of State / Local plans to the licensee plans so as to assure the capability to take emergency actions.
(e)
Conduct test exercise.
4.
The licensee shall take actions required to demonstrate that planned decon,
tamination and/or restoration operations at TMI-2 will not impact safe operations at TMI-1. The licensee shall provide separation and/or isolation of TMI 1/2 radioactive liquid transfer lines, fuel handling areas, ventila-tion systems, and sampling lines.
Effluent monitoring instruments shall have the capability of discriminating between effluents resulting from Unit 1 or Unit 2 operations.
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. The licensee shall demonstrate that the waste management capability, includ-5.
ing storage and processing, for solid, liquid, and gaseous wastes is adequate to assure safe operation of TMI-1, and that TMI-l waste handling capability is not relied on by operations at TMI-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.
Isstres to be addressed include the adequacy of groups providing safety review and operational advice, the management and technical capability and training of operations. staff, the adequacy of the operational Quality Assurance ' program and the facility procedures, and the capability of.important support organizations such as Health physics and plant Maintenance.
7.
The licensee shall demonstrate his financial capability to operate TMI-l at the TMI 1/2 ccmplex.
8.
The licensee shall comply with the Category A recommendations as specified in Table B-1 of NUREG-0578.
The Ccmmission has additional concerns, which, though they need not be resolved prior to resumption of operation at Three Mile Island Unit 1, must be satisfactorily addressed in a timely manner. The Commission's Director of Nuclear Reactor Regulation (NRR) has recommended that the following actions (the "long-term actions")
be required of the licensee to resolve these concerns and permit a finding cf reasonable assurance of the safety of long-term operation. These are:
1.
submit a failure mcde and effects analysis of the ICS to the NRC staff as scan as practicable; 2.
give continued attention to transient analysis and procedures for management of small breaks by a formal program set up to assure timel,y;ac;jon of these g iv'* '
.- matters; 3.
comply with the Category B recommendations as specified in Table B-1 of NUREG-0578; and, 4
improve emergency preparedness in accordance with the following:
(a) modify emergency plans to address changing capabilities of plant instrumenta tion,
(b) extend the capability to take appropriate emergency actions for the population around the site to a distance of ten miles.
In addition, the licensee shall also provide, but not prior to restart, timely response and implementation of longer term recommendations which may result from the Lessons Learned Task Force as well as recommendations that may arise from the Presidential Commission, the NRC's ongoing investigations, and other studies unless such recom-mendations are determined by the Director of the Office of Nuclear Reactor Regulation to be requi-ed orior to restart.
III. Accordingly, pursuant to the Atomic Energy Act of 1954, as amer.ded, and the Commission's rules and regulations in 10 C.F.R., it is hereby ordered that:
the licensee shall maintain TMI-l in a cold shutdown condition until satisfactory resolu-tion of the concerns, identified above, which led the Commission to suspend the liceosee's authority to operate.
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Tbil-1 RESTART I SSU ES
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BULLETINS AND ORDERS l_ (7
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EhiERGENCY PREPAREDNESS
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hiAN AGEhlEN:T C AP ABl Li TY 0
FlNANCIAL CAPABIL1TY 0
LESSONS LEARNED g G 45 u
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ASSESS STATE / LOCAL PLANS TO LICENSEE PLANS FACILITY INTERACTION' 0
NC IMPACT ON-SAFETY FROM TMI-2 OPERATIONS 0
SEP AR AT10N' 0F CERTAI N> COMMON FEATU RES 0
EFFLU ENT 01 SCRI MI NkTl DNr C APkBI LI TY 0
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CAPABILITY OF SUPPORT ORBANIZATIONS LESSONS LEARNED 0
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FAILORE MODE AND EFFECTS ANALYSIS OF iCS
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