ML20035B394

From kanterella
Jump to navigation Jump to search
Summary of 930324 Meeting W/Util & NUMARC in Rockville,Md to Discuss Emergency Action Levels
ML20035B394
Person / Time
Site: Beaver Valley
Issue date: 03/25/1993
From: Edison G
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9304010284
Download: ML20035B394 (45)
v • d • e


Text

5 March 25, 1993 ocket Nos. 50-334 and 50-412 LICENSEE: Duquesne Light Company FACILITY: Beaver Valley Units 1 and 2

SUBJECT:

SUMMARY

OF MEETING HELD ON MARCH 24, 1993 TO DISCUSS EMERGENCY ACTION LEVELS WITH NUMARC AND DUQUESNE LIGHT COMPANY A meeting was held on March 24, 1993, at the NRC, One White Flint North in Rockville, Maryland, with Duquesne Light Company (DLC) and NUMARC. The purpose of the meeting was to discuss the progress made by NUMARC and DLC in making improvements to PWR emergency action levels (EALs).

DLC described their efforts to develop revised EALs for PWRs based upon NUMARC's methodology (enclosure 1). DLC has volunteered to serve as a pilot program for the effort. DLC is acting as a lead plant to complete revisions to the EALs which would eventually lead to a proposal to replace current EALs with revised EALs.

It is expected that further discussions will be needed before a formal proposal for revised EALs is submitted.

A list of meeting attendees is provided as enclosure 2.

Gordon/S /E. Edison, Senior Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/ enclosures:

See next page

. DISTRIBUTION w/ enclosures:

DISTRIBUTION w/ enclosure 2 only:

Docket _ File T. Murley/F. Miraglia F. Kantor NRC & Local PDRs J. Partlow S. Boynton PDI-3 Reading S. Varga E. McCabe J. Linville, RI J. Calvo E. Fox G. Edison W. Butler A. Mohseni T. Clark B. Erickson OGC J. O'Brien E. Jordan ACRS (10)

F.),aughlin V. McCree, EDO m

PM:PDI-3N D:PDI-3/ I b OFFICE LA:PDI-3 TYlYa [

GEdison:fnw WButler i

WE 2_;/23/93 J bd93

"?> / f/93

/ /

/ /

i DME 0FFICIAL RECORD COPY

'~

FILENAME: BV324MT. SUM r mn rp r rtryp m eggy 3

g a g gu a n a"g

,i L

k;

'f

+

- /pa asoq

~

'o UNITED STATES E '],.c 'k NUCLEAR REGULATORY COMMISSION

j

{-.

WASHINGTON, D. C. 20555

(

~

/

March 25, 1993 j

Docket Nos. 50-334 and 50-412_

f i

LICENSEE: Duquesne Light Company i

FACILITY: Beaver Valley Units 1 and 2 i

SUBJECT:

SUMMARY

OF MEETING HELD ON MARCH 24, 1993 TO DISCUSS EMERGENCY ACTION LEVELS WITH NUMARC AND DUQUESNE LIGHT COMPANY A meeting was held on March 24, 1993, at the NRC, One White Flint North in Rockville, Maryland, with Duquesne Light Company (DLC) and NUMARC. The

{

purpose of the meeting was to discuss the progress made by NUMARC and DLC in making improvements to PWR emergency action levels (EAls).

I i

DLC described their efforts to develop revised EALs for PWRs based upon NUMARC's methodology (enclosure 1). DLC has volunteered to serve as a pilot i

program for the effort. DLC is acting as a lead plant to complete revisions to the EAls which would eventually lead to a proposal to replace. current EALs i

with revised Eats. -It is expected that further discussions will be needed l

before a formal proposal for revised EAls is submitted.

1 A list-of meeting attendees is provided as enclosure 2.

b

-Gordon E. Edison, Senior Project Manager -

Project Directorate'l Division of. Reactor Projects --I/II Office of Nuclear Reactor Regulation j

Enclosures:

j As stated I

cc w/ enclosures:

1 See next page l

.5 i

I l

f

L

. o.

.f Beaver Valley Power Station.

Units 1 & 2 Duquesne Light. Company cc:

Jay E. Silberg, Esquire Bureau of. Radiation Protection Shaw, Pittman, Potts & Trowbridge Pennsylvania Department of 2300 N Street, NW.

Environmental Resources Washington, DC 20037 ATTN:

R. Barkanic Post Office Box 2063 Nelson Tonet, Manager Harrisburg, Pennsylvania 17120 Nuclear Safety a

Duquesne Light Company Mayor of the Borrough of; Post Office Box'4 Shippingport Shippingport, Pennsylvania 15077 Post Office Box 3 Shippingport, Pennsylvania 15077 Commissioner Roy M. Smith West Virginia Department of Labor Regional Administrator, Region 1 Building 3, Room 319L U.S. Nuclear Regulatory Commission Capitol Complex 475 Allendale Road Charleston, West Virginia 25305 King of Prussia, Pennsylvania 19406 John D. Borrows Resident Inspector Director, Utilities Department U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 181 180 East Broad Street

.Shippingport,-Pennsylvania 15077 Columbus, Ohio 43266-0573 Director, Pennsylvania Emergency Mr. J. D. Sieber,' Senior Vice Management Agency President and Chief Nuclear Post Office Box 3321 Officer Harrisburg, Pennsylvania 17105-3321 Nuclear Power Division

.Duquesne Light Company Ohio EPA-DERR Post Office Box 4 ATTN: Zack A. Clayton Shippingport, PA.

15077-0004-Post Office Box 1049 Columbus, Ohio 43266-0149 i

N L V ARC 3hNR 3i o: EA_s 3asec on 3eaver Va ey 0wer S:a: ion ni::.

3 MV Ducuesne 4

7 T Likjy:

AF March 24,1993

in~: ROC UC~: ion

, ~ _

_ ~

Ur30se o= :,e ai o~: program 3

o a 03en "orum "or ciscussion 3 an~: speci"ics a

Wes~:inglouse 2652 VW: 3_oop 3WR SuJa:mosaleric con ~:ainmen~:

Commercia 03 era: ion :.97L

.1dV. q uesne 4

7 F Lidn A

Procedure Entry l

l l

l l

1 i

l 9 An off-normal event has occurred, or, l

e An action step in a plant operating procedure or emergency operating procedure directs user to this procedure t

4 1

4

'h ;:

h((

t NUMARC PWR pilot !!AIS :-

BNEALO1.PH2

.+,.,,es

,,,.g7

=~re--

we**-

ie-i-

v-- - = - --'-- ='-

  • +P
  • ----s

-- e

' - * * * ~ - * - - -

'=--+W*--

e * *- - ' - ~ ~ - - = - - -

- - - - * * *- ** - * - * " ' = - - = - * - = " " ' - - - - - - - - - - - - - - - - - -

t

=

S I

A f

I

'I D

s l

iP e

t i

i W

r P

C o

l l

A g

M e

U s

N t

L aC A

nt s

n o

E-i e

t v

i f

nE o

g g

o n

ci e

et a s

r RiL t

u niA e

n E

t vI c

e6 7

S 3

7 u

e e

e r

5 2 h[

t

  1. ($

S 1

Seven Recognition Categories e Tab 1-Fission Product Barrier Matrix e Tab 2 System Degradation e Tab 3 Loss of Power

e. Tab 4 Hazards and ED Judgement e Tab 5 Destructive Nmmena e Tab 6 Shutdown Systems Degradation e Tab 7 Radiological
  • [IQ hI$j NUM AItC l'W11 I'llDT I!AIS

=-

BNEAlot PH2

..--.----2.

..-.--,-----,--.,------,-a

..w,----c+-...~

.-----v.

.-.--,--,--n,----

av,,

~~,. -,, -, - -n-

--n,v--.,--.

77 EALs u

i G Each has a CRITERION, printed in bold type b

$ Correspond to NUMARC " Initiating Events" 1

O Each has one.or more INDICATORS

l h!

$w yg; NUMARC PWR Pil.OT I!AIS

=-

CRITERION 1

O Identifies the emergency condition and any numeric values which define the c'ondition e All classifications are based on ED assessment that the CRITERION has been met e Assessments triggered by INDICATORS l

.e Assessment time limited to 15 minutes

ong, "Qg5 NUM AllC PWit l>llDi'1 AIS

=

on m o,en2

. -..,,.,., ~. _,..

3.y.v.,.

4,._

.,,r,,,.s,

,m., _ _.

...-.......m~

4__..,

4 INDICATOR e A specific instrumentation reading, a physical condition, a report by plant personnel, or other evidence that the associated CRITERION may be exceeded e Upon recognition of an INDICATOR ED performs assessment against the CRITERION O Assessment may be simple (e.g., channel check) or detailed (e.g., dose projection)

O Assessment time limited to 15 minutes s%

'hyF NUM AllC PWR PIIDi'liAIS

=

Selection of INDICATORS l

l 0 Goal to provide unambiguous guidance to assist with assessment of CRITERION O Emergency Directors are not limited by INDICATORS provided.

l l

O If condition presents a different set of INDICATORS that, in the ED judgment exceeds the CRITERION, the declaration can be made d%

  • ))llb l

BNEALot.PR2 l

Implementation Cons.derations i

e Common Plant Conditions e Mode Applicability e Transient Events O Declaration Timing and Assessment e EAL Bases l

Q?lf l

D, S

.. p;o NUM AllC l'W R l'IlOT li AI.S

l^

Common Plant Conditions i

i e Senior NSS makes declaration and assumes role of ED e If common condition results in a higher classification at one unit, the NSS at the affected unit makes declaration and assumes ED role.

$'h%

., -,.,_,--,.,~,..,.-..-.,. -..- _.....-,....__

Mode Applicability e Mode that existed at time or recognition, prior to protective system or operator action, is controlling 4 If a lower mode is reached prior to declaration, the mode that existed at the time of recognition is controlling

$ Fission product matrix (FPM) applicable only in modes 1-4 4 Shutdown events do not escalate to FPM even if mode 4 is entered as a result of a heatup i

i l

+Yisfj, l

' r; p -

NUM ARC l'WR PILOT li AIS :-

i BNEALot PH2

Transient Events 4

h l

l 9 If EAL does not specify a duration, classification i

is made as soon as ED assessment concludes that the CRITERIONis exceeded 1

e If EAL specifies a duration, classification is made when the ED assessment concludes that the duration is, or will be, exceeded, whichever is sooner

$ e.g., no' success path to. rectify condition prior to duration elapsing.

l

$* '0 pg5 NUM AllC l' Wit I'll.OT I! AIS :-

osenoirna.

.-.mmm--.m... --m

...~-,

.....m..

... ~.. -......,...

w,_..

,sw--4

,,.._m+,.

,o.m..

Transient Events O If the condition is rectified before the duration is exceeded, then -the particular CRITERION is-not exceeded

$ Lower classification events may apply 1

e If condition is recognized well after event, no i

l emergency is declared l

$ e.g., condition identified in routine log review i

$ 10 CFR 50.72 reporting may be required l

d%

"?tgF NUM AllC l'Wil I'llOT liAlS =

BNEALO1PH2

. ~

Transient Events O If classification was warranted, but condition is rectified prior to declaration and notification:

$ Consider possible effects of rectified event-

-$ For UE, make declaration. Termination maybe in same notification

$ For others, declare event and activate ERFs. Evaluate termination criteria dye

'34%

NUMARC PWR pilot I!AIS :-,

enmoira2

l Declaration Timing and Assessment 1

O Assessment starts when INDICATOR is recognized t

e Assessment time is limited to 15 minutes, except:

$ If EAL specifies duration, assessment period is the same length as, and runs concurrently with, the duration

$ If duration is already exceeded, or unknown, complete assessment within 15 minutes l

l O If assessment i.s not complete, then event is classified on basis of validINDICATOR 0$!

k

"{$jg[;$

NUM ARC PWR PilDi'!!AIS

=

l EAL Bases

  • Will be available as Chapter 4 of EPP
  • Provide guidance for " gray" events oValuable asset for training e Baseline for subsequent revisions et 3;p NUM ARC PWR Pil.OT 1:AlS :-

gngw,,,n2 m

i

______________m_,._,._m._.-

. _. ~, -..,.-

.w.,

.-....w-.---,

v.

,,.....,.,.,,.....e-r,,,,,,

,,,_,..,.m....m.,-....,,,,--

..r-

, ev..ia:lons J

r i ure o~

Reac~:or ro:ec: ion 3

a a

nc usion o~

E3A LOC Jose Quan~:i~:ies a

.dV Ducuesne 47 liji:

V oci"ica~: ions l

o S:eam Genera:or ~~uae Ru1:ure anc Je"ini~: ion o" 3

r:e Area _mergency. n

le -ission roc uc:

S.

1 i

3arrier Va:rix o _oss o" runc: ion - re"ects neec :o acress inaaii:y :o

" achieve" co c slu:cown as we as ma'in~:ain o RCS _ea< age - S3 i~:irr:0 nicen:i"iec anc Icerr:i"iec ea< age anc incoraora:es reasonale :ime 'ac: ion s:a:emerr:)::o icen:i"y or s:o3 nicenti"iec ea< age dV Ducuesne A

7 F Lif1:

A

.._.._.._.-._..____._._._____..._-.._._____.____.._-____m___.__-

Ac ci~: ions a Acci: ion o" Si:e S3eciic nstrumen~:a: ion:

_e:cown Racia: ion Voni:or-C ac Jamage Reac:or Vessel Wa:er _ eve - RCS 3arrier o _oss o" runc: ion 4:GE} - Recuncarr: :o a ma'or sequence :1rougl

le ission Procuc: 3arrier r

nc usion o~ Sa"e:y _imi: 'L E) o rire 4:GE anc SAE)- nc usion o" A :erna:e sa ~e a

slu:cown 3rocecure usage anc cegraca: ion

.1d%Ir Ducuesne

'Af likji;

Acc : ons Non,~:,/

m ii ire 'JE?- nc usion o"im30r:arr: auicings aeyonc

le a

3 o:ec:ec Area r

a _oss o" JC L E? - Accec in Voces :.,2,3, & L a Slu:cown Sys:em Jegraca: ion !:A )- nc usion o" curren: uncerstancing o" cirec: ion anc sco3e o" :le slu:cown EA_s. 4:~~1is may be moci"iec suas:an:ia y, 3asec on incustry anc regu a:ory review?

7 fLisa A

i Considerations Applicable to all FPM Classifications O An INDICATOR is considered met if the stated threshold has been, or is, reached or exceeded on the basis of confirmed observation or VALID L

instrument readings e An INDICATOR is considered m.et if the parameter is indeterminate, and the existance l

of the condition can not be reasonably discounted e -

w

$1[h NUM AllC l' Wit l>llOT liAIS 1 eng wirn2

Considerations Applicable to t

all FPM Classifications e An INDICATOR is considered met if, in the ED judgment, the INDICATOR will be met imminently (i.e., within 1-2 hours in the absence of a viable success path). Classification is made when this determination is made 1

e A LOSS constitutes a POTENTIAL LOSS; a POTENTIAL LOSS does not constitute a LOSS g

W 5;g NUM ARC l'WR PILOT EAIS :-

,,,,y

....... _.. _ _... _. - _., _.... _ -.. _. -... _. ~.. _.. _.. _. _.. _ -.. _ _. _ _. _..

- ~

Classification Criteria eUE

  • LOSS or POTENTIAL LOSS of Containment Barrier e Alert
  • LOSS or POTENTIAL LOSS of Fuel Clad Barrier or 1
  • LOSS or POTENTIAL LOSS of RCS Barrier 31f6 SREALO1PH2

Classification Criteria

  • Site Area Emergency 4 LOSS of any two barriers
  • POTENTIAL LOSS of any two barriers 16 6
  • Modification from NUMARC All barriers weighted equally at this level NUMARC weighted Containment less Slightly more conservative, but simpler 50 %

"$g;/;S NUM ARC PWR PilDl' !!AIS

=

m u>na

Classification Criteria e General Emergency

$ LOSS of any two barrier and POTENTIAL LOSS of the third, or

  1. LOSS of all three barriers

'n w

%9 NUM AllC l' Wit I'llcl' 1:Al.S

.om e irna

Fuel Clad

1. Critical Safety Function Status I

Potentist LOSS

^ '"

= " ' ' ' " " ' '

Wili :.'.',, e !s"?'

nro parn

&R.

2. Average of Five Highest CETCs

., Peterdial LOSS o,..w the. tpno r o w,emen ros r OR.

--~~~t e CSF Status

=====m

~.-,o,<es, P'1." #.-.;"

.o R.

4. Primary Cootent Activity Level j

Potential LOSS f

eRx Water Level e.c.,

ORCS Activity

.,R.

5. Letdown MonMor indleotton

~~" "

e Letdown Monitor --

:==

~ - -

addition OR-

6. Contelnment Redletton Monitors Peterdlet Loss e Containment va- ---.

=

~=e ~=-

~

Radiation

n 4.f2 312 eED Judgment 4 R.
7. Emergency Director Judgement Any cent eiion that, m the p@. ant of the NSS4_0, f

atienics loss or prantent loss at ine Fu.i tied hereme wepperable to the tnrtecators bstekt atxwe i

?I Q 6 4e se i

m E

~;r!.*k :2[b NUM ARC l>W11l'IlOT !!AlS =

ludEALotPR2

.2 RCS Barrie e

RCS Barr1er 1 Critical Safety Function Status Potentist LOSS pNy 7%,,

W appeesh.

csr RE D PA TM

-O R.

2. Reactor Vessel Water Loval LOSS Potential LOSS

_, ~. _

-OR-o CSF Status Po,.

,.,Le,S

, - - - - :==

e Rx Water Level --

=~~;-

addition

=--

OR-e RCS Leak Rate

"~':: ""*"'"; -,, Less o.

e Pri-to-Sec Leak --

=.

?--

modified S. Containment Radiation Monitors Lost Potenstat Loss e Containment

~

e.

Radiation I..F--

eED Judgment

-O R.

6. Ernergency Diroctor Judgement Any condsen that, m the judg.mem of the NSS/EO.

amsto se.,rparerwiniwsorinencsherr ree asc mpa toin..

tnesi,stede w.

,ew

%f

<:' fi g <

NUM AI(C PWit Pil.OT I!AlS 1 UNEALO1.PH2

-~..

Containment

~

i?""Lt::-

Potentlei <OSS c.at.n es c sF mE o paTM Barraer

=+

g 4R.

2. Centelnmerit Ptossure / Hydro 0*n Cone.

e CNMT Pressure /

re su g,r 10P

.I e.ep.n NOT c.no.wm I

es, ewe 9 98G we LOC A cane.an.

esth bee. than an. 09.amd Hydrogen

.O R -

Concentration

3. Containment isolation Status

<o.,

~...., _

e CNMT isolation

~--

-O R.

4. Containment Bypass Status

<o.,

~.-,.,<e L'?;;"O =.";,

r.=;".11*=

e CNMT Bypass -

=r.,er:-==5=~

Wf A.l,ta.pame*F.h CN 64 84 Ale'm sa RM RW f gel A.

addition & modified

.. ~..

_-~

~

-O R.

t

....... R...,_,,n C.

._ent e Significant

~-,-se Radioactivity in

r=

CNMT iY eED Judgment My condifers that. m the judgement of the NSSE D,

> ~,

ir$.ates los a or poemreat loss of the Cent einment be.vgr comparable to the r@cators bstati ate e s

yn NUM ARC PWR PILOT I!ALS :-

usttoi em

g A

.__;2,

_u.m O

99

%a 4

d l

mp 1

..n tumn C

E

. y,,

e,

e s

BT h

h 3

i wva!!!ja!!

0 g.

y

' :.. ' a s= 4. b g M 5

!1 4.a

2 I

m o

gy 20 2

. p.(

3.. a.o a

< s.e

..~

G Z

is s o-.i Wti" (5

g

v
11

$g 5

-*3est 2

. ' r V6 on it 22v

.f M )

bf m a paim T

?:

e te n.

M 3kp_s g

  • Q=4 ts a-Q

<.-,t.s. a og s,e s.

'
f}

E

[E esAs

.o

.M

.n

,:C

}IE ocO a

m c:l; i

+1 :

8 ! U, E

are.;

M

.M O

.,.k? =;5.)

Q ggc

,gW i j

}

YY h,

han w, as

,.o

01 ros M

Ej?.:nn$.

Q

'N

$d y

gM q$:<n

.3 EJsE M

E 7

pues(

Q E

s g

10.;5 Q-1 18 o

s E;g Ij !) ]

ep4 d

f j" gis 5

i$ $

$?.73 p.h P'o=4

l{

@f I,,

d:f 5 4)

^$"

gi E8

/,IId9

,S, diia f==

h o %u a

L o.

a:.

g EdSfjf

(?J2 3

k k

a 1

Sys:em,egraca~: ion s

g og.-~m.m..~as-g ;+ 43 wegw t/

o Loss of Instrumentation i

o Loss of Function - Recuncan: acci: ion or GE

- Sa e:y unc: ions incor3 ora:ec in:o SAE r

- nabii:y :o Aclieve Co c Slu:cown in:o A er:

a Failure of Reactor Protection - Accec a new A er:

revious A er: as E

3 a Fuel Clad Degradation d%.Duc uesne

'A f U d'-

_[

t Sys~:em Jegraca~:'on <Corf::

a RCS Unidentified Leakage - nc uces reasonaa e

ime ~ or cerr:iica: ion or :ermina: ion o~ :le ea<

a RCS Identifed Leakage alnability to Reach Required Shutdown within Tech.

Spec. Limits a Safety Limit Exceeded - Accec l.

L aTurbine Failure a Main Steam Line Break d%.Duc uesne 7 F IJ f1:

A 5

.,---.,e

.,,_,.,p

,,.4-w,.

g

.____.,,.y v.

v.

y 4.

,,._..,_.__,u___,_____,,__.__m__

y

^

'l i

3 OSS O 0Wer o Loss of AC Power 03s}

o Loss of AC LShu:cown?

o Loss of DC - Adcec Voces :.,2,3, & G 4

.1dV Ducuesne 4

"F f Lis A

n.

,.--.,---.e

-e,

-,+-- - * -

  • r-m,

-v-,r i-----.---

r m s

.. ~. -

. - ~ -,

-azarcs anc ED ucgemerr:

o Fire - Accec GE and SAE or A :erna:e Sa e Slu:cown a Explosions a Flammable Gas atoxic Gas a Control Room Evacuation

_is: o ecui3 men: usec

o aro:ec: Cri:ica Sa e:y unc: ions o Security o Emergency Director Judgement

.1dVt uesne

'Af'

e n

s eu n

qij a

l n

%F P

e m

d7A o

n e

h ev s

a i

r

-c C

u e

h r

l i

t h

ws

-s c

g a

ei o

r e

jH L

C o

J e

l l

r i

e e

k P

v v

a f

a o/e e

r

~

u t

f L

L c

qd h

a a

r r

r r

e t

n c

e et r

r r

v v

a a

TARoiiiW R

E a

a a

a a

a

t L

t

~

^

s s

t t

s n

n s

l t

e e

e n

v g

u e

e n

v lf u

i E

f T

l l

E ff n

d g

s E

o n

i a

n u

d t

I o

a I

i i

e u

d e

i l

t s

a a

q a

u i

i G

R F

T t

o e

e e

in I

ruo sp 2H P

u9 to F

s3 LA ER G

Liquid Effluents -- Criteria e GE:

n/a i

e SAE:

n/a e A.lert: Unplanned release exceeds 200 times T/S for > 15 minutes t

e UE:

Unplanned release exceeds 2 times T/S for

>60 minutes

$ti' 7%

=

7p y:

g WMAK MW MIOT !!AIS :-

uneAwt enz

Radiation Levels -- Alert e Control Room or PAF dose rates exceed 15 mR/hr for >15 minutes O Dose rates impede access

  1. Only areas that contain equipment that must be operated manually

-$ NUREG-0578 areas specifically included along with access routes 5

Wie NUM AllC l> Wit l>l101'. liAIS :-

.DNEALO1PR2

l Radiation Levels -- Alert l

1 I

O For areas not normally High Radiation Areas, I

threshold is 100 mR/hr WRWP coverage changes l

l 9 For areas that are High Radiation Areas, threshold is 5 R/hr

$ Emergency exposures may be involved QffL Top NUMARC PWR PilDr EAIS =-

- muoi.pn2

<-....-,-..4

.**m...--..~a,

,.e,

,..s,s

....... -,,.., -..... - -.. ~..<~.....E 4

,~.v.rm..+..

.ym+,4

.i...,. +,,

.-oh.w--_v,,

.--Ee%~-..,.w

,3, v-%+

e

4

+A a

b4 m

m 4ae.+-w.e-a, e

- - ~ ~, -

O O 4

-)

oI o

k i

B i

M 9

N A

t E

>c g

U-

. c::

p eW h

'Z f

CC

+a o

. W 4

YCY au mo g +o O

Q

.M

+2 N

g M %

g E

~

Q O

,e m

.= W W

NA

~

/

g 1

NN Q

im g 4>.5

'O e 1

t e

es >

$% ?l

? &" 9l M

kQ W

.,J e -

)

l

~

l lif enseu n Qd i.

l V4 7 dF"A s

4 A

E 7

0 n

s

~

_ mn w

t e

w n

o t

a s

o )n )n d

c d

y yt wwn t

m u

u S

u o

od i

l h

a l

n d

d e

S t

t c

S wh uR i

u t

o h

i r d

ySS gC t

r

(

u o(

n t

4 h

t CCi n

l S

nADd a

e n

t f

vf f

a r

o n

o oH ev I

s s

s d

l sS s

s e

a oC o

o u

n L

R L

L F

l a

0 a

a 0

a

!lfll fll)

J I

MEETING WITH DUQUESNE LIGHT COMPANY I

AND NUMARC TO DISCUSS EMERGENCY ACTION LEVELS. MARCH 24. 1993 NAME ORGANIZATION G. Edison NRR/NRC R. J. Barkanic PA DER M. W. Kirk NUMARC F. J. Laughlin NRC RI F. Kantor NRR/DRSS/EPB Scott Boynton NRE/DRSS/PEPB Ebe McCabe NRC/RI/DRSS/FRSSB/EPS Edwin F. Fox, Jr.

NRR/DRSS/PEPB/ES t

Aby Mohseni NRR/DRSS/PEPB Bob Erickson NRR/DRSS Jim Eaton NUMARC Jim O'Brien NRR/DRSS Steve Lavie DLC Alan Nelson NUMARC Ernest Chatfield Duquesne Light Co.

Roy Brosi Duquesne Light Co.

2 k

5 l

l I

I I

e-

-

Retrieved from "https://kanterella.com/w/index.php?title=ML20035B394&oldid=4578125"