ML19199A363

Forwards IE Bulletin 79-05A Re Incident at TMI

ML19199A363
Person / Time
Site:	Crane
Issue date:	04/05/1979
From:	Moseley N, Mosely N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:	Engelken R, Grier B, James Keppler, James O'Reilly, Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
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ML19199A365	List: ML19199A363
References
NUDOCS 7904170039
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UNITED STATES

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g NUC:. EAR REGULATORY cCMMISSION

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April 5,1979

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MEMORA'iCUM FOR:

S. H. Grier, Director, Region I i

J. P. O'Reilly, Director, Regicn II J. G. Xepoler, Director, Regien III K. V. Seyfrit, Director, Region IV R. H. F.ngelken, Ci rector, Regica 'l m,

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Nor an C. Meseley, Director, Division of Reactor FFCM:

Operations Inspection, CIE m-y SL*3 JECT:

IE BULLETIN 79-05A, NUCLEAR IllCICE'{T AT THREE MILE s+,

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ISLAND The subject IE Sullecin shceld be dispatched for acticn by April 5, 1979, to all SW pcwer reac cr facilities with an operating licensa.

I Tne Bulletin must be faxed to SW facilities by April 5.

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subject bulletin and enciesures shculd also be dispatched fer infer =a-tion to all other pcwer reacter facilities with an operating license h

and te all pcuer reactor facilities with a constructica permit.

'L; 591 Tne texL uI i.he Eulletin, Encicsures thereto and draft 1st ars 4c-the Q

licensee are enciesed fer this pur;cse.

Tne continuing Preliminary

_m Notificaticns of the incider.t should cantinue cc be forsarded as they are received in accordance wid the transmittal meterandum fer

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IE Eulletin 79-05.

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,._Semar((.Mosaiey,Directar

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Office of Inscecticn and Enforcement

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Enclosures.

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Draft Transmittal Letter

-4 to all 3G Operating Licensees

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Dr:ft Transmit al Latter

_as to all etner Cperating Licensees and Ccastmctica Fernic Heiders.

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IE Bulletin Mc.79-05A.

(w/ enclosures - 2) e

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N-CONTACT:

D. C. Kickpatrick, IE

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(Oraft letter to B&W pcwer reactor facilities with an operating license.)

m s g-w IE Bulletin No.79-05A

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Enclosed is IE Bulletin No.79-05A, which requires action by you with c.s

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regard to your pcwer reacter facility (tes) with an cperating license.

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Should you have any questions regarding this Bulletin or the action

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required by you, please contact this office.

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Sincerely,

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(Oraft letter to all power reactor facilities with an operating license or a construction permit.)

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Mdressee:

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The enciesed Bulletin 79-05A'is forwarded to you for information.

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Written resp nse is required.

If you desire additional informtion

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regarding this matter, please c:ntact this office.

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Sincerely, h:

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UNITED STATES NUCLEAR REGULATORY COM9.ISSION

'I 0FFICE OF-INSPECTION AND ENFORCEMENT l[;

WASHINGTON, CC 20555 W

$f APRIL 5, 1979-IE Sulletin 79-05A HUCLEAR INCIDENT AT THREE MILE tsLAND - SUPPLEv.ENT E

W'.

Descripticn of Circ:nstacces:

s*,c es Preliminary informatien received by the NRC since issuance cf IE Bulletin 79-05 en April 1,1979 has identified six potential human, design and mechanical failures which resulted in the core damage and radiation releases at the Three Mile Island Unit 2 r.uclear F et.

The T

informatien and actions in this supplemenc clarify and extano iriginal Bulletin and transmit a preliminary chronology of the TMI acciden:

FGe through the first 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> (Enclosure 1).

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At the time of the initiating event, loss of feedwater, both of the auxiliary feedwater trains were valved cut of service.

5.~

2.

The cressurizer electromatic relief valve, which opened during the initial pressure surge, failed to close when the pressure

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decreased below the actuation level.

3.

Fo11cwing rapid depressurization of the pressurizar, the pressurizer 2_..

level indication may have lead to erronecus inferences of high

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level in the reactor c:olant systam.

The pressurizer level indicati apparently led the operaters to prematurely terminate hign pressure injection flow, even though substantiai voids existed in the reac:Or y(([.

c:clant system.

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Secause the containment does not isolate on high pre.csure injection (HPI) initiation, the highly radicactive water frcra the relief valve discharge was pumped out of the containment by the automatic

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initiation of a transfer pump.

This water entered the radicactive

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waste treatment system in the auxiliary 'uilding where scme of it overflowed to the ficor.

Outgassing frua this watar and discharge through the auxiliary building ventilation system and filters was

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the principal source of the offsite release of radioactive nooie gases.

5.

Subsecuently, the high pressure injecticn system was intermittently

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cperated attempting co control primary coolant invent 0ry losses through the electromatic relief valve, apparently based en pressurizer levei indicati0n.

Due to the presence of steam and/cr

.J, noncendensible voids elsewhere in the reactor c:clant system, this led to a further reduction in primary ccolant inventory.

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Ni-IE Eulletin 79-05A April 5, 1979 i

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6.

Tripping of reacter ecolant pumps during the ccurse of the transient, to protect against pump damage due to pump vibraticn, led to fuel damage since voids in the reactor coolant system prevented natural

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e dsh Actions To Be Taken by Licensees:

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Fct all Babecek and 'Jilecx pressurized water reacter facilities with an

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acerating license (the actions specified belcw replace these specified m,,.

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tr. IE 3ullecin 75-05):

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(This iten clarifies and expands upcn item I. Of IE Sulletin 79-05.)

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In additien to the review cf circumstances described in Encicsure 1 of IE Eulletin 79-05, review the enciesed preliminary cnrencicqy of

][ll' understanding the secuence of events to ensure agains: such an the TMI-2 3/28/79 acci dent.

This review should be directed tcward

.u 120 accident at ycur fac'ili;y(ies),

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2.

(This itan clarifies and expands upon item 2. of !E Bulletin 79-C5.)

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Review any transients similar to the Davis Besse event (Enclosure 2 cf IE Eulletin 79-05) and any others which cencain si=ilar elements

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from the enclosed chrenc1cgy (Enclosure 1) which have c-ccurred at J,

your facility (fes).

If any significant deviations frca expected

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performance are identified in your review, previde details and an analysis of the safety significance together with a descriptien of any ccrrective actions taken.

Reference may be made te previcus information provided to the NRC, if appropriate, in respcnding ::

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(This item clarifies item 3. of II Sullecin 79-05.)

3 Review the actions Ptquired by your opei*ating pt Cedures for Ccping

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with transients and accidents, with particular attentien to:

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Sn; a.

Recognition of the possibility of forming voids in the primary ecolant system large encugh to ccmcrcmise the core ccoling capability, especially natural circulation capability.

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b.

Operator action recuired to prevent the formation of such

'~3-voids.

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Operator action required to enhance ccre cccling in the even-

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such voids are foraad.

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(This item clarifies and expands upcn item 4. cf IE Bulletin 79-05 c7 Review the acticr.: directed by the operating procedures and training

?'m instructicns te ensure that:

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a.

Operators do not override automatic actions of engineered E52 shfety features.

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b.

Operating precedures currently, or are revised tc, specify that if the high pressure injecticn (HPI) system has been

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autcmat1cally actuated because of law > essure conditien, it must remain in cperation until eitbe :

(1)

Ecth icw pressure injection (LPI) pumes are in cperatien

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and ficwing at a rate in excess of 1000 gpm each and the

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situatien nas been stable for 20 minutes, or

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The HPI systam has been in cperat'en fer 20 minutes, and all het and ccid leg temperatures are at least 50 degrees belev the saturation tamperaturt for the F-#

existing RCS pressure.

If 50 degree subcce'.ing cannet 9h"'

be mainclinea after HPI cutoff, the HPI shall be N$.,F reactivated.

.'2' c.

Operating peccedures currently, er are revised to, specify 9.i: ~

that in the event of HPI initiat cn, with react 0r ccclant

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pumps (RCP) operating, at least cne RCP per loop shall remain operating.

A'E-d.

Operators are proviced additional informatien and 'nstructions to not rely upon pressurizer level indicatien alene, but to aise examine pressurizer pressure and other plant parameter

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indicaticns in evaluating plan conditiens, e.g., water inventory in the reactor primary system.

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5.

(This item revisas item 5. cf IE Sulletin 79-05.)

se-Verify that emergency feedwater valves are in the cpen pcsition in accordance with iten 8 below.

Also, review all safety-reiated

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valve pcsitions and pcsitioning requirements to assure that

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valves are pcsiticned (cpen er closed) in a r.anner te ensure the 7""

prepee operatica of engir.eered safety fea, 'es.

Also review related precedures, such. as these for maintenance and testing, 9^

to ensure that such valves are returned to their ccrrect pcsitions

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fcilowing necessary manipulattens, mk&..

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IE Bulletin 79-05A April 5, 1979 Page 4 of 5 5.

Review the containment isolation initiation design and precedures,

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and prepare and implement all changes necessary to cause containment isolation of all lines whose isolation dees net degrade core eccling

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capability upon autcmatic initiation of safety injection.

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7.

For manual valves or manually-operated motor-driven valves which I'

cculd defeat or comprcmise the flow of auxiliary feedwater to the a'i h steam generators, prepare and implement procedures which:

w require that such valves be lecked in their correct position; a.

or b.

require other similar positive position controls.

8.

prepare and implec.L, immediately procedures which assure that two independent steam generator auxiliary feedwater ficw paths, each wit.'

100% ficw capacity, are operable at any time when heat remcyal from the primary system is through the steam generaters.

When two inde-pendent 100% capacity ficw paths are not available, the capacity shall be restored within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the plant shall be placed in a cooling mcde which dces not rely on steam generators for cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

When at least one 100 capacity flow path is not available, the reactor shall be made subcritical within ene hour and the facility placed in a shutdown cooling mcde which does not rely on steam generators fcr cooling within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or at the maximum safe shutdown rate.

9.

(This item reYises item 6 of IE Bulle in 79-05.)

Review your operating modes and procedures for all systems designed to transfer ;ctentially radioactive gases and liquids out of the primary containment to assure that undesired pumping of radicactive liquids and gases wi.ll not occur inadvertently.

In particular, ensure'that such an occurrence would not be caused by the resetting of engineered safety features instrumentation.

List all such systems and indicate:

a.

Whether interlocks exist to prevent transfer when high radiatica indication exists, and

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Whether such systems are isolated by the centainment isolation I signal.

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h IE Sulletin 79-05A April 5,1979 page 5 of 5 k

10.

Review and modify as necessary your maintenance and test procedures to ensure that they require:

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Verificatien, by inspection, of the cperability of redundant I

safety-related systems prior to the remaval of any safety-

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related system fra service.

be e, r. s.

b.

Verification of the cperability of all safety-related systems when they are returned to service folicwing maittenance or testing 3L c.

A means of notifying involved reactor operating persennel whenever a safety-related system is removed frem and returned to service.

11.

All cperating and maintenance personnel shculd be mace aware of the extreme seriousness and censequences of the simultaneous blocking of both auxiliary feedwacer trains at che Three Mile Island Unit 2 plant and other acticns taken during the early phases of the accident.

12.

Review your prcept reporting precedures for NRC notification to assure very early notifica:icn of serious events.

For Babccck and Wilecx pressurized water reactor facilities with an operating Ticense, respond to Items 1, 2, 3, 4.a and 5 by April 11, 1979.

Since these items are substantially the same as these specified in IE Bulletin 79-05, the required date fer response has nut been changed.

Respend to Items 4.5 thrcush 1.d and 6 through 12 by April 15, 1979.

Reports should be submitted to the Director of the apprcpriate NRC Regional Office and a ccpy shculd be forwarded to the NRC Office of Inspection and Enforcement, Divisica of Reac:cr Operatiens Inspecticn, Washington, DC 20555.

Fer all other reactors with an operating license or censtructicn permit, this Bulletin is for information purposes and no written respense is required.

Approved by GAO, S 180225 (R0072); clearance expires 7-31-80.

Approval I

was given under a blanket clearance specifically for identified generic problems.

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Enclosures:

1.

preliminary Chrenclegy of TMI-2 3/38/79 Accident Until Core Ccoling Restered.

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2.

..st of IE Bulletins issued in last 12 mcnthi. '?;g

Encicsure 1 to IE Bulletin 79-05A spril 5,1979 c=

PRELIMINARY

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lif, CHRCNCLCGY OF TMI-2 3/28/79 ACCIDENT

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UNTIL CCRE CCCLING RESTORED n[.,

TIME (Approximate)

EVENT f_ii'

-about 4 AM Loss of Ccndensate Pump 1

(t = 0)

Less cf Feedwater Turbine Trip t = 3-6 sec.

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Electrr.atic relief valve opens (2255 psi) to relieve pressure in RCS t = 9-12 sec.

Reacter trip cn high RCS pressure (2355 psi) t = 12-15 sec.

RCS pressure decays to 2205 psi (relief valve shculd have clcsed) t = 15 sec.

RCS het leg temperature peaks at 611 degrees F 2147 psi (450 psi over saturacien) t = 30 sec.

All three auxiliary feedwater pumps running at pressure (Pumps 2A and 23 star ed at turbine trip).

No ficw was injected since discharge valves were cicsed, t = 1 min.

Pressurizer level indic: tion begins to rise rapidly t = 1 min.

Steam Generators A and 3 seccndar/ level very icw - drying cut over next couple of minutes..

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t = 2 min.

ECCS initiation (liPI) at 1500 psi

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t = 4 - 11 min.

Pressurizer level cff scale - high - ene HPI punc manually tripped at abcut 4 min.

30 sec.

Second pump tripped at abcut 10 min. 30 sec.

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l RCS flashes as pressure bottx.s cut at t = 6 min.

1350 psig (Het leg temperature of

'...,I 584 degrees F) j3 o

t - 7 min., 30 sec.

Reactor building sump pump care en.

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C TIME EVENT 5

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t = 8 min.

Auxiliary feedwater ficw is initiated by opening cicsed valves b'"_:.

t = 8 min. 18 sec.

Steam Generater B pressure reached minimum m+

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t = 3 min. 21 sec.

Steam Generator A pressura starts to esecyer

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t = 11 min.

Pressuriree level indication cenes back cn scale and cecreases 03W t = 11-12 min.

Makeup pump (ECCS HPI ficw) restarted by Es cperators

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RC Drain / Quench Tank rupture disk bicws at t = 15 min.

190 psig (setpoint 200 psig) due te centinuec discharge cf electrcmatic relief valve

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t 50 min.

System parameters stabili:ed in saturated ccndition at abcut 1015 psig and about M-550 degrees F.

N t = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />,15 min.

'Cperator trips RC pumps in Lcep B idh-i t = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 40 min.

IUperator trips RC pumps in Lcep A m-

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t = 1-3/4 - 2 hcurs CCRE BEGINS HEAT UP TRANSIENT - Hot leg temperature begins to rise to 520 degrees F (off scale within 14 minutes) and cold leg temperature drops to 150 degrees F.

(HPIwater)

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t = 2.3 hcur Electrccatic relief valve isolated by

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operator after S.G.-B isclated to prevent 34.

leakage

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t = 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> RCS pressure increases to 2150 psi and electrematic relief valve cpened

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t = 3.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> RC drain tank pressure spike of 5 psig t = 3.8 hcurs RC drain tank pressure spike of 11 psi -

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RCS pressure 1750; containment pressure

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increases frca 1 to 3 psig t = 5 hcurs Peak centainment pressure of 4.5 psig

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t = 5 - 6 hcurs

RCS pressure increased frcm 1250 psi to

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lto21C0 psi

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TIME

GENT t = 7,5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Operator cpens electrocatic relief valve t:

E depressurize RCS to attempt initiation cf k1 R lR at t.00 psi hjx t = 8 - 9 hcurs RCS pressure decreases to about 500 psi Ij Ccre Ficed Tanks partially discharge M

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.t = 10 hcur 28 psig centainment pressure spike, centainard sprays initiated and s:cpped after 500 gal cf1 NaCH injected (abcut 2 minutes of operatien) t = 13.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Electrcmatic relief valve closed to repressuri RCS, collapse voids, and star: RC pug t = 13.5 - 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> RCS pressure increased frem 650 psi to 23CO ps t = 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> RC pu:r.c in Locp A started, het leg ter.:erature decreases to 550 degrees F, and cold leg temperature increases to 400 degrees F.

indicating ficw through steam generator Thereafter S/G "A" steaming to condenscr Ccndensor vacuum re-established RCS cooled to abcut 250 degrees F.,

1000 psi Mcw(4/4)

High radiation in contair. ment All core thermecouples less than 460 degrees F.

Using pressurizer vent valve with small makeup ficw Slcw cecidewn RB pressure negative h"3 i

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i TEL.*GRAF. TO 3 5*r7 LICENSEES '

(AUDRfSSEES ON PAGE 2) m FRCH NUCLEAR EEGULATORY CCFS.ISSICN a

M THE.CC.W ISSICN'S DIRECTOR' OF INSPECTION AND ENFORCIMENT UAS d

ISSUED A BCLI.I"~27 DATED APRIL 1, 197 9, AND IS ISSUING A h.*!

SECCND SULLETIN THIS EVENING ':.t ALL LICENSEES OF NUC' EAR

',c2 POWER PLANTS INCCRPORATING STEAM SU??LY SYSTEM DESICNS 1.

ESSENTIALLY IDENTICAL TO THAT C" UNIT NC. 2 CF THE THREE v, w.- - - -,

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a TO FOLLOW CERTAIN PRCCECURES ANO DEVELOP PARTICULAR IN?CFS_ATICE IN CCNNECTICN WITE PRCTECTING AGAINST EVENTS SIMI*AR TO THOSE AT TERIE MI'd ISLAND.

'THE TUFSCSE Cr THIS MESSAGE IS TC UNDERSCORE THE SERIOUSNESS WITH WHICH THE COMMISSION' VIEWS THESE MATTERS AND TEE IMPORTANC t

WE ATTACH TO YCUR PRCyST AND COMPLETE COMPLI; dice W!TH TEE DIRECTOR'S 3CLLETINS.

i hf. TROST THAT TCU WILL EXERT YCUR EIST EFFORTS TO COMPLY WITH THE AFCREME2;TIONED DIRECTOR' S EULLETINS COMPLETII,Y AND IN A TIMY FASIIION.

TO THAT END, WE EXPECT THAT YOU W'..L p

b ASSIGN TO THESE TASRS AMPLE PERSONNEL, SUPPORTENG SERVICES,

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AND A2TY C'I.'ER NECESSARY RESOURCES.

A 1O

@F OCSEPU M. HINDRIE I_'5 CHAIRMAN 9m a

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Enclosure IE Sulletin No.79-05A April 5, 1979 Page 1 of 3 5

LISTING OF IE BULLETINS f5 ISSUED IN LAST TdELVE PONTHS g

Ei Bulletin Subject Date Issued Issued To g

No.

u 78-05 Malfunctioning of 4/14/78 All Pcwer Reacter 1

Circuit Breaker Facilities with an Auxiliary Cencacc OL or CP Hechanism-General Model CR105X 78-05 Defective Cutle.r-5/31/78 All Pcwsr Reacter Ha.mer, Type M Relays Facilities with an With DC Coils OL or CP 78-07 Protection afforded 6/12/78 All Power Reacter by Air-Line Resp;irators Facilities with an and Supplied-Air.Hccds OL, all class E and F; Research Reacters wit' an OL, all Fuel Cycle Facilities with an OL and all Priority 1.

Material Licensees 78-08 Radiation Leveis frca S/12/78 All Pcwer and Fuel Element Transfer Research Reactor Tubes Facilities with a Fuel Elesent transfer tde and an OL.

78-09 WR Orywell Leakage 6/14/79 AT1 EWR Pcwer Paths Associated: with Reactor Facilities Inadequate Dryvell with an OL or CP g

Ciasures y

T 78-10 Bergen-Paterson 6/27/78 All SWR Pcwer Hydraulic Sheck Reacter Facilities jB Suppressor Accumulater with an OL cr CF

[F5 Spring Coils fC L

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Toledo Edison Company Edisen Pia::a Is 300. Madison Ave.

W:

Toledo, Ohio 43552

[yl mIL Florid; Pcwer Corporation 3201 34th St. South St. Petersburg, 'Fl a.

33733 Duke Power Ccepany 422 S. Church St.

Charlotte, N. C.

22242 Sacramento Municioal Utility District 6201 South St.

Sacramento, Calif.

15830 Arkansas Pcwer & Licht Co.

9th St. at Louisiana Little Rock, Ark.

72203 Metropolitan Edison Cccoany 2800 Pottsville Pike g

Reading, FA.

19620 gr 2ebk

6..',

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IE Sulletin Nc.79-05A Enclosure April 5, 1979 Page 2 of 3

,_,b LISTING OF IE SULLETINS d

ISSUED IN LAST TnELVE MONTris Bulletin Subject Date Issued Issued To p2 78-11 Examination of Park I 7/21/78 EWR Pcver Reac:cr Centainment Torus Facilities fer i

Welds action:

?each Bettem 2 and 3, Quad Cities 1 and 2, Hatch 1, Menti -

cello and Ver.ent Yankae 78-12 Atypical Weld Material 9/29/78 All Pever Reacter in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-12A Atycical Wald Material 11/24/78 All Pcver Reacter in Reactor Pressure Facilities with an Vessel Welds OL cr CP 78-123 Atypical Veld Ma'terial 3/19/79 All Pcw r Reactor in Reacter Pressure Facilities with an Vessel Velds OL or C?

78-13 Failures In Scurce Heads 10/27/78 All general and of Kay-Ray, Inc., Gauges specific licensees Mcdels 7050, 70503, 7051, with the subject 70513, 7C50, 70508, 7061 Kay-Ray, Inc.

and 70613 gauges 78-14 Deterioration of Suna-H 12/19/78 All GE EWR facilitic Cccconents In ASCO with an CL or C?

~

Sol'enoids kp 79-01 Environmental Qualifica-2/3/79 All Pever Reacter f

tien of Class IE. Equipment Facilities dth an M CL er CP

[y in TE iML i

3 s '-' 'j'.)

Jy2

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IE Bulletin No.79-05A Encicsure April 5,1979 Page 3 of 3 7

LISTING OF IE EULLETINS

[]

ISSUED IN LAST TWELVE HONTHS Om Bulletin Subject Date Issued Issued To

$3 No.

9U En r's E[~

79-02 Pipe Suppert Base Plate 3/2/79 All Power Reactor 1

Designs Using Concrete Facilities witn an Expansion Ancher Ecits OL cr CP

~

79-03 Longitudinal Weld Defects 3/12/79 All Pever Reae:Or In ASME SA-312 Type 304 Facilities with an Stainless Steel Pipe Specis OL er CP Manufactured By Y ungstown Weiding and Engineering Cc.

79-04 Incorrect Weights for 3/30/79 All Pewer Reacter Swing Check Valves Facilities with an Manufactured by Velan OL or C?

Engineering Corporation 79-05 Nuclear Incident 4/1/73 All B&W Pe*er at Three Mile Island Reactor Facilities with an OL P

3 Q*

' J ic lA fNtx N

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