NRC Generic Letter 1992-09
OR%,RE0L 4 e
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555
- 0c.
December 31, 1992 TO: ALL HOLDERS OF OPERATING LICENSES OR CONSTRUCTION PERMITS FOR
NUCLEAR POWER REACTORS
SUBJECT: LIMITED PARTICIPATION BY NRC IN THE IAEA INTERNATIONAL NUCLEAR EVENT
SCALE (GENERIC LETTER 92-09)
PURPOSE
The U. S. Nuclear Regulatory Commission (NRC) is issuing this generic letter to inform licensees of its recent decision to participate in the International Nuclear Event Scale (INES) of the International Atomic Energy Agency (IAEA).
The NRC decided to participate in this program in a limited way to foster international cooperation. The NRC expects that the limited use of INES will have a negligible effect on its licensees or on State and local governments.
The participation of the NRC is not intended to affect emergency classifi- cations, event reporting to the NRC, or communications with the public.
Nevertheless, usage of the INES could lead to confusion with the existing four-level emergency response scale used in the United States. This generic letter discusses the measures and conditions of the limited participation to prevent any adverse effect. It.supersedes the previous position of the NRC
not to participate in the INES program (letter from E. L. Jordan, Director, NRC Office for Analysis and Evaluation of Operational Data, to NRC licensees, dated August 22, 1990).
DESCRIPTION OF THE SCALE
The INES is a tool intended to promptly and consistently communicate to the public the safety significance of reported events at nuclear installations by providing a common terminology among the nuclear community, the media, and the public for describing the events. The INES was designed by an international group of experts convened jointly by the IAEA and the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development. The group was guided in its work by the findings of a series of international meetings held to discuss general principles underlying such a scale. The INES also reflects the experience gained from the use of similar scales in France and Japan as well as from consideration of possible scales in several other countries.
Events are classified in the INES at several levels. Events of greater safety significance (levels 4-7) are termed "accidents," events of lesser safety significance (levels 1-3) are termed "incidents," and events of no safety significance (level 0 or below scale) are termed "out-of-scale deviations."
9212280250
POD& TOoc'ooo
- - December 31, 1992 DISCUSSION OF LIMITED NRC PARTICIPATION
The IAEA adopted certain precautions on the use of the INES.
They are given in a leaflet describing the structure and use of the INES (Attachment licensees or state or local governments do not need detailed 1). NRC
event rating because the NRC will complete and submit. event instructions for (Attachment 2) to the IAEA. rating forms The NRC will limit its participation by classifying and submitting for events at nuclear power plants that are classified as an forms only on the emergency response scale used in the United States. alert or higher Not every alert will necessarily have an INES classification, as some may be rated below the INES scale.
When the NRC receives a report of an event, it will delay the INES level number for about a week after termination of the assignment of an event, subsequent developments in assigning the number. This time delay to consider prevent any confusion with the U.S. emergency classification. will help notify State and local governments and the affected licensee -The NRC will classification. The NRC will not request of any of these partiesof its INES
concurrence with the NRC classification. The NRC does not plan a review or press release associated with the classification, but will to issue a the transmitted event rating~form to the concerned licensee provide copies of Public Document Room. and to the NRC
The NRC remains bound to the early notification and assistance formally approved by the IAEA General Conference in September conventions conventions provide for an international exchange of information, 1986. These assistance during a nuclear accident or serious radiological data, and emergency.
BACKFIT DISCUSSION
This generic letter conveys information about the participation agency of the United States, in the international program of the NRC, an of the IAEA for classification of nuclear events. By this generic letter, the not request any licensee or applicant to submit information NRC staff does not recommend any new regulatory action, and does not modify to the NRC, does regulatory position of the NRC staff. Consequently, this genericany existing not represent a backfit. letter does
Generic Letter 92-09 - 3 - Decemb i 31, 1992 This generic letter requires no specific action or written response. If you have any questions about this information, please contact the technical contact listed below, who is the NRC INES Coordinator.
Ames G. Partlow Atsociate Director for Projects Office of Nuclear Reactor Regulation TECHNICAL
CONTACT
- Denwood F. Ross, Jr., Deputy Director Office for Analysis and Evaluation of Operational Data U. S. Nuclear Regulatory Commission Mail Stop 3701 MNBB
Washington, D.C. 20555 Telephone (301) 492-7361 Attachments:
1. INES Description
2. INES Event Rating Form
3. List of Recently Issued Generic Letters S e - F I to Of E -z
,01 The International Nuclear Event Scale For prompt communication of safety significance I
I U
MAJOR ACCIDENT
. 1 I SERIOUS ACCIDENT
ACCIDENT WITH OFF-SITE RISK
ACCIDENT
ACCIDENT WITHOUT SIGNIFICANT
OFF-SITE RISK
_____m m -
El SERIOUS INCIDENT
INCIDENT
N
INOIDENT
I
_ _ _
I .
ANOMALY
.
DEVIATION BELOW SCALE
NO SAFETY SIGNIFICANCE
w or, General description of the sal.
- A lthough V sa scab i used bor an instanstions, h is ptqalcafy hnpoabfar even i ccur which Involve the release to the envwom ciconsiderable qu anttis of radioactive m t eri atsm types MkdWta il
1The intational Nudw Event Scale (NES) isa *d lo promptly don. For th Instalations, upper evel of Viesale would not be and W tllte0tycommunicate lb to Public the Safety sgfcae d applicable, Then include reanch ractors, un radlatsd io e A el r e p ote ev nsat nuce ri saltos.y p ti g v nsito p o e treatment facitltes, and waste storag sties specv, VW Scat. Can aM ommnon understanding among the nuclear
- inusa accidents or oW events which re no related hice community, the medfa and the Public. ft was designed by ant international or r'WioplOgcal opeuationS wend classfied and wetermedocut at scale"
ouP c eXPeU Convened Jointly by the internatonal Aomic negy For examPle, awthough e t asociated with a tubine or gen ea can genc ( ndthe u l En y ncVe otg nidsation affetd safety rftd equipm t, faultsaffet only the dvallablty dia r Economkc Coopeaon end Devopment p wn guided hi ts t ub in Or gener w o u ld b e Classifi d as o u f s cL eS. S k mlan, by Viefde meetings held hi discuss such a fir erglo be consIdersd out of scae when they do not wolve ner pnps u g scale. The Sceab flec t any po b a dioloical hazard and do n affect Vi safety is ge e eacales e In France and Jua weE tm considention d possible scal In sevea other cwies.
- The Scale is not approprtat a fth basis r selectin eventsor WiVaflya~ppltiedtr aftilperliod eedbac* OF operationa expeience, " hmPOtan lsson Cm cite be hcsetfy evensat nuclearpowu lernt omevents OFrelatively for Wsgficane plants, 3 countries participated in the tr and inthW ationi agencle and use counin montred prog The Scale operated successfuly and I* Uisto appropit hi Use the Scale IDcomper safety penfomano now ha been made availabe br ormi adoption by each country. The unong count ies. Each counny ha dif e anangem et b reportin Scale slag has been extended and adapted la enable It lo be appled ia mino events hi fte pubc and his difficu to ernsr procis international nuclea istalltions associated with the clv nucger industry end to any consieoncy In rat even at tie boundy between lesvOand v I.
events ocrog durin Vi transpIt d radioctive maerbd I and r *omr The statisticaly sma nutntr of such eve, with vlbit fom Yew hi thug bsmlltes. VW.mIaka I dfcui 10 providem eaninfuli nrnsional comparsons Events We uasified on Vie Scale at seven levels. Thek deait 5 Althoughboedly omprable, nule aend radIdoogical safty an atetsd ar shown oppofte wfith amples df the classification d criteria anld i terminology Use1d IDdescrib them vry from coutr~y lb nuclear en which hav occurred In the past at nuca insallations The ountry. The bNha been designed tot ai m of th act ounl lowe level (1-3) weemed incidents. and the IPPer levels (4-7 acl- dent Even which hv rig safely sincance w dc fid . level W
below scale and we tMed deviation Events wich hav no saety levance we term dout of cale.
The stucture of the Scale is shown oppoits, Inthe bira cia muts withkeywor Thew used wenot Ind to be prc defnt Ea criterion i defined In dewS wthi an DM Users' Manuel. Events armconslered In rm ofthree afety attribute or afa4r ee by Examples of classfed nuclear events eech of Vie lwmw l hoped, on-ell Impact, and defInce hI depth d_~
- The 190oacident at the Chernob nudger power plant in the The eecon column "Itm rea i events meeirg hi cis Soviet union (now in th Urlne) ld wieprd eronetal and oite nlasee od radicectifft. Sinc Vil is the only coneequence having a hUmn= health effects. t is VOM claselled as Level 7.
dirt effect on the publ such relases we undestandably Of pmhldi
- The 137 accident as Vhe KItym reprooesg plW in th Soviet conern Ths, the bot pot inthi oolmmrepesents an -g Vie mor posed pson c t an etimaed radiaton does nu _eically Union (nW In ssiW)ld 10 lar ol-se r s e E mergency m ea equivalent to about ore4e of the annuaudose lkm for tie public; fthi Including evauaon of the population wer 10 lhio seris heIM
classfied as led 3 Such a dose is aleo typically abou t on he eftcts Bsd onthedoff-st ImpaT Of this event is casfd a Level L
average anual dues nicelved fom natura beckgrornd nsdiaticn, The
- T* 1957 accident at th ak- e aplil reactor pRe at highest level IS a major nudger acdden with widespread healt and Windacale (now Selfleld hfalty in the Unite IMgdcm Involved an envirwonmen consequencs etIn a releas d iogdiw veflsl prouct. Sa w co the cd lt Thetrd colhum consers the oefa hpocdof the aver ThIs hoaed 11Sclassified a Love L
category Cover a range toni leve 2 (Contamination andb overeposur
- The 197 sde atThree MU ind th U ed e rd d wor.) *a hi levelS (severe pant damg such
- a core melt). in sevrel damaged reatr cr. T he of-sdrelaecrdlctvyw Al nuerw acillties am designed So that a euccesson of safety very lmd. The nt Icassfied is as LvelS.baged ca th ons impac WY" act prevent major on-site, or cf-sit knwd a the extent d th
- The 1973 accdnt at the Windace rteprocesn plant in the sae an s povided generaly wil be comensurt with Vie potential kf United ngdom (now Sefaflekd involved a release radictive mai an and Df-h impact. Thes sa lyer mudt a faNl beo Substantial nto a plnt oprn g wm s rea di an e cthein reacon hI
off-sts or on-ite consequences ci. The provision of ths safety lyes poess vessel 1bis classified as Leve 4. based on rt onsie knpac terd "defence in depth". The bth umn d t matrx et o incidetsat nuclew intalations or dungthe trawtaticn cf radoectiv,
- The 130 accident at th SWnt-uren nucer power p matenua Inwhicth defence Indepth prvisions have been degaded. Fra Meeled In parti danma I re r orme, but thr w2s m This cAm sparm the Incident Waft I-& extrna on elease
.l~te hinth ci radioactivity.N is
1 classfied U Level 4. based on the An eventwti ha disctrisftcsreprsente bymaorethanone
01l1s101 IS
- Th e1963 -ide nt at VieRA2 crtic 2am ently in u c Ak Bu, OkaX always classified at the highest b ll~ acorIng inany one leel Aretine an ecidenra power exulon du lo nonobservance of safet rues during a m r modification sequence, resutted In the death of th peroxr, who was probably 3cr 4 m way. Assessment of th does absorbed by the viftmindicate21 y orthe gamma deo bogethe wit
22 Gy brVe neuon dose. The event is classifiedd Laval 4, based on
- Th 1 a the Yndeund dincidnt pow plnt in Spain did Using the Scale not result In an external release d irdioactivty. nr was tr edamage te t reectOr sO or contamination an st Howevr, the damae h0bt plant's safety syt ms due hi fr degaded the defenc dpth Sign -
- Although t Scal is designed for pa us folowing an eve, canfy. The nt isclasified as Level 3. based on th defence-hi epth thr wl be occaowhen a bgw tme-ca ibrequkd hi undesta drilriorL
and rate the consequences c an evenL i these we dounau, a .
- Thvast majorty repore d rsound hib below Level provisina rating wN be given wit confirmation at a Mwadate. N Isalso Posstbl that Iss reaul of furthe information, an evei imay require Although no exa Ples Of th s events we given here, couni es uing Vie reclassdcation. Scab may indhdualy wish to provide e pls co evts at thee bwer
11w.L
>i f mdoctv nuderWX xis kwtlltin orduig i trnsor ci rratdiatv ma matrils dts N em ergency pln i n nra g en tswo be e m nte d. T he Secao l no tbe used asp ar rm a eme ncrge in fo y arra rg emn enla .
4 ji .. iv p1--o// 11- Basic structure of the scale
& gOmn h maw uaT b'dm*cOnt
&wde Doetald deilf am prvid hi 0fiES Mism' maW
CRITERIA OR SAFETY ATTRIBUTES
.OFFE _ A CE IN DEPTH
7 MAO RELEASE:
MAJOR WIDESPREAD HEALTH AND
ACDENT EVIRONMENTAL EFFEC
6 SIGNIFICANT RELEASE:
SROS UIKEY TO REOUIRE RILL
ACIDNTIMPLEMENTATO OF
PLANNED
COUNTERMEASURES
5 U MFIED RELEASE: SEVERE DAMAGE TO
ACCIDENT UKELY TO REQUIRE PARTIAL REACTOR CORE1 WITH OFF-iSrE RISK IMPLEMENTATION OF RADIOLOGICAL BARRIERS
PLANNED
COUNTERMEASURES
4 .MINOR RELEASE. PUBLIC SIGNIFICANT DAMAGE
ACWDET WITHOUT EXPOSURE OF THE ORDER TO REACTOR
SIGNIFICANT OF PRESCRIBED uMITS COREfRADOLOGKIAL
OFF-SITE RISK BARRIERSIFATAL EXPOSURE
OF A WORKER
S VERY SMALL RELEASE: SEVERE SPREAD OF NEAR ACCIDENT-
SERlKUS INCIDENT PUBWC EXPOSURE AT A CONTAMMINAT1ONACUTE NO SAFETY LAYERS
FRACTION OF HEALTH EFFECTS TO A REMAJNING
PRESCRIBED LMITS WORKER
SIGNIFICANT SPAEAD OF INCDENTS WITH
INCDENT CONTAMINATION SIGNIFICANT FAILURES
cOVEREXOSURE OF A IN SAFETY PROVISIONS
WORKER
ANOMALY IIEYOND THE
ANOMA.LY * ATHORISED
OPERATING REGIME
I I
BELOW SCALE EVENT NO 'SAFETY G1CNIFICAN E
DEVIA.I I
OUTOFSCALEEVENT NO SAFETY RELEVANCE
I I .
THE IN\iRNATIONAL NUCLEAR EVEl4VSCALE
for prompt communication of saety significance LEVEL l_ DESCRIPTOR _ _ EXAMPLES
ACCIDEN7S MAJOR ACCRENO , 9 .lnrw ref oet alo large factil tofjadloace materIal
7 . facility (e.9. th core of a power reactor). This would typically InvolveIna large Chernobyl NPP,
mitur o shoat nd king-lived radioactive fission products in quantitles a USSR (nowIn logically equivalent to more than tens of thousands terabecquerels of radio. Ukrale t984
.odina*131). Such a release would result in the possibility of effects; delayed health effects over a wide are possibly invomng acute heath one country, lng-term environmental consequences. more than a SERIOUS ACCIDENT
- External release of radioactive material (In quantities radiologically lent to the order of thousands to tens of thousands of tarabquerels ofequlva- Kyshtym lodln`131) Such a releai would be likely to result In full Implementation Reprocessing countermeasures covered by local emergency plans to limit serious health of Plant affects. USSR (now In Russia), 1957
3 ACCIDENT WITH
- External release of radioactive material (in quantities radilogically OFF-SITE RISK lent to thoorder of hundreds to thousards of terabequearel of idine-31). equlva. Windscale Pile, Such a release would be likely to result In partial Implementation UK, 1957 measures covered by emergency plans to lessen the likelihood of ofhealth counter- effects.
- Severe damage to the nuclear facility. This may involv severe a large traction of the core ola power reactor, a major crIticality damage to Ttree Mile Island, major fire or exposion releasing 1agquantitis of radioactivity within accident or a USA, 1979 the Installation.
4 ACCIDENT
- External release of radioactivity resulting hI a dose to the WITHOUT lndiv dual off-site of the order of a few milislever s.4 With suchmost exposed SIGNIFICANT a release the need for off-site protective actions would be generally unlikely ecept OFF-SIE RISK for local od controi possibly Wndscal
- Signiicant damage to the nucear facility. Such an accident might damage to nuclear plant leading to major on-elt recovey include Reprocessing partial core melt In a power reactor and comparable eventsproblems such as at non-reactor Plant, UK, 1973 Instaihfona Saint-Laurent NPP.
France, 1980
a Irradiation of one or more workertwhich r sult In an overexposure a high probability of early death o where Buence Aires CrItical Assembly, Argentina, 1983 INCHDENTS SERIOUS INCIDENT
- External release of radioactivity above authortsed Imits, resulting
3 to tho most exposed indhvdual off site of the order of ternts of In a dose With such a releha off-site protective measures may not be needed. mIllisievert.
- On-sit events resulting In doses to workers sufficient health effects andfor an event resulting In a severe spreadtoofcause acute for example S few thousand terabecquerls of activity releasedcontaminatiob containment where the material can be returned to a satisfactoryInstoragea secondary aea
- Incidents In which a further failure of safety systems could lead to accident conditions, or a situation in which safety systems would be unable Vandellos NPP,
an accident If certain Intliators were to occur. to prevent Spain, 1989
2 INCIDENT
- incidents wMth sgnif".nt ha1lur. In safety provisions but with defence In depth remal.nd sufficient g to cove with additional failures.
- An event resulting In a dose to a worker exceeding a statutory annual dose limit andlor an event which leads to the presence of significant ties of radioactivity In the Installation hI amss not expected by designquanti- which require correctie action. and ANOMALY
- Anomaly beyond the authorlsed operating regime. This equipment failure, human eiro or prooedural Inadequacies.may be due to (Such anmnalies should be distinguished from situations where operational limits tlons re nodexceeded and which are properly managed in accordance and condi-
_dequate procedures. These we typically with
"below scale").
BELOW SCALE/ DEVIATION
ZERO NO SAFETY SIGNIFICANCE
the dee m &WVmga of 1soCke dm s viAaJb dos* Mm.
tius *% tosI oft Wpb cm a be axpvmzsdt, mm*s Growswonaf duh&W
nW knjt&orhed by NaftW auftift Int~nitIMIAtl AtoMIC EneWg Agemiy C~IOECo Nuctea Ene Age"
ItV Wagnerltrasis 5
92-01414 A A-t400 Vienna, Austri _ 38. 8oUlvad Sucpeat W75016 PagIS, Franc,
K> K'
THE INTERNATIONAL NUCLEAR EVENT SCALE (INS)
- EVENT RATING FORM (ERF)
to be sent to IAEA WAGRAMERSTRASSE 6, P.O. BOX 100, A-1400 VtEN4k AUSTRIA
cu. i_4 i mAfR I c. opjiTn&A %npmA FACMSI 43 1 23073 TEPIIO 43 1 20 26
' EVENT DATE
EV
lTITE
auaOFw BLON .wE SCAE DEENCE MEMTh RATING R
6rm.ME ATTpIBE WA _
DoOE SCAO c 1 5 44 1
_ FACIUTY FACILITY
ASPECTS OF SIGNIFICANCE TO THE PUBULC YES NO
ACCIDENT 0 INCIDENT 0 DEVIATION 0
RADIOACTIVE RELEASES OFF-SITE
RADIOACTIVE RELEASES ON-SITE 0 0
0 0
WORKERS INJURED BY RADIATON
WORKERS INJURED PHYSICALLY 0 0
PLANT SAFETY IS UNDER CONTROL 0 0
THE EVENT REPORTED IS A DISCOVERY OF A DEFICIENCY
BY ROUTINE SURVEILLANCE 0 0
A PRESS RELEASE WAS MADE OF YES, PLEASE ATTACH I) 0 0
SHORT DESCRIPTION OF THE EVENT:.
low_
CONT PEMON FMR AMOVSS
RJRNM *6ORMAT1ON PHN
FAX
EnoT MAIM AUD Of0
0WLEEM D0,ILU - w
.P ASE ATUAM AFwONAL *aoAIMTMN ON JUSTIrATION CF -j I
- 1e z
44t OF RECENTLY ISSUED GENERIC LkEERS
Generic Letter No. Date of Subject Issuance Issued To
92-08 THERMO-LAG 330-1 12/17/92 ALL HOLDERS OF
OPERATING LICENSES
OR CONSTRUCTION
PERMITS FOR NPRs
92-07 OFFICE OF NUCLEAR REACTOR 10/10/92 ALL HOLDERS OF
REGULATION REORGANIZATION
OPERATING LICENSES
OR CONSTRUCTION
PERMITS FOR NPRs
83-28 REQUIRED ACTIONS BASED ON
SUPPLEMENT 1 10/07/92 ALL LIGHT-WATER
GENERIC IMPLICATIONS OF SALEM
ATWS EVENTS REACTOR LICENSEES
AND APPLICANTS
92-06 OPERATOR LICENSING NATIONAL 09/06/92 ALL POWER REACTOR
EXAMINATION SCHEDULE
LICENSEES AND
APPLICANTS FOR AN
OPERATING LICENSE
92-05 NRC WORKSHOP ON THE 09/04/92 ALL HOLDERS OF
SYSTEMATIC ASSESSMENT OF
LICENSEE PERFORMANCE OP LICENSES OR
(SALP) PROGRAM CONST. PERMITS FOR
NUCLEAR PWR REACTORS
92-04 RESOLUTION OF THE ISSUES 08/19/92 ALL BWR LICENSEES
RELATED TO REACTOR VESSEL
WATER LEVEL INSTRUMENTATION IN FOF OPERATING
BWRs PURSUANT TO 1OCFR50.54(F) REACTORS
90-02 ALTERNATIVE REQUIREMENTS
SUPPLEMENT 1 07/31/92 ALL LWR LICENSEES
FOR FUEL ASSEMBLIES IN THE
DESIGN FEATURES SECTION OF AND APPLICANTS
TECHNICAL SPECIFICATIONS
87-02 SAFETY EVALUATION REPORT
SUPPLEMENT1 05/22/92 ALL USI A-46 NO. 2 ON SQUG GENERIC
IMPLEMENTATION PROCEDURE, LICENSEES WHO
REVISION 2. ARE SQUG MEMBERS
92-03 COMPILATION OF THE CURRENT 03/19/92 ALL NUCLEAR POWER
LICENSING BASIS: REQUEST
FOR VOLUNTARY PARTICIPATION PLANT APPLICANTS
IN PILOT PROGRAM AND LICENSEES
N
. *
K1- Generic Letter 92-09 - 3 - December 31, 1992 This generic letter requires no specific action or written response. If you have any questions about this information, please contact the technical contact listed below, who is the NRC INES Coordinator.
James G. Partlow Associate Director for ProJects Office of Nuclear Reactor Regulation Technical contact: Denwood F. Ross, Jr., Deputy Director Office for Analysis and Evaluation of Operational Data U. S. Nuclear Regulatory Commission Mail Stop 3701 MNBB
Washington, D.C. 20555 Telephone (301) 492-7361 Attachments:
1. INES Description
2. INES Event Rating Form
3. List of Recently Issued Generic Letters DISTRIBUTION:
Central Files NRC PDR
OGCB/DORS r/f CVHodge KBrockman DAllison Document Name:
- OGCB:DORS:NRR
INESCALE.WPG
- C:OGCB:DORS:NRR
- SEE PREVIOUS CONCURRENCE
- IRB:AEOD *AEOD
4
0. RY:NRR
CVHodge:mkm GHMarcus KBrockman DAllison (BjlG'mes
12/02/92 12/07/92 12/02/92 12/02/92 12/1I/92
- D:DRSS:NRR ADPR % J
FJCongel
12/10/92
. I . I
Generic Letter 92- - 3 -
This generic letter requires no specific action or written response. If you have any questions about this information, please contact the technical contact listed below, who is the NRC INES Coordinator.
James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Technical contact: Denwood F. Ross, Jr., Deputy Director Office for Analysis and Evaluation of Operational Data U. S. Nuclear Regulatory Commission Mal I Stop 3U7U1 MM~ A
Washington, D.C. 20555 Telephone ((301) 492-7361 Attachments:
1. INES DescriptiorI
2. List of Recentl3 Issued Ger eric Letters I
I
Document Name: INESCALE.WPG *SEE PREVIOUS CONCURRENCE
- OGCB:DORS:NRR *C:OGCB:DORS:NRR *IRB:AEOD *AEOD D:DORS:NRR
CVHodge:mkm GHMarcus KBrockman DAliison BKGrimesfA
12/02/92 12/07/92 12/02/92 12/02/92 12/ /92 D:DRSS:NRj ADPR
FJCongel JGPartlow
1210/92 12/ /92 flAe
. I . ?
Generic Letter 92- - 3 -
This generic letter requires no specific action or written response. If you have any questions about this information, please contact the technical contact listed below, who is the NRC INES Coordinator.
James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Technical contact: I)enwood F. Ross, Jr., AEOD
(301) 492-7361 Attachments:
1. INES Description
2. List of Recently Issued Generic Letters L~Ve e1we61r Document Name:
OGCB:DORS:NRR !:DORS:NRR IRB:AEOD D:DORS:NRR
CVHodge:mkm KBrockman DAllison BKGrimes
12/a/92 12/o2/92 12,p L/92 12/ /92 ADPR
JGPartlow
12/ /92