ML20066H143

From kanterella
Jump to navigation Jump to search
Responds to NRC Re Violations Noted in Insp Repts 50-352/90-28 & 50-353/90-28 on 901203-07.Corrective Actions: Procedure HP-715 Re Trailer Dose Rates Revised & Technician Counseled
ML20066H143
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 02/12/1991
From: Leitch G
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9102200187
Download: ML20066H143 (4)


Text

- _ _ _ -

g.,.

,10CFR 2o201 1;d.

PHILADELPHIA ELECTRIC: COMPANY LIML*RICM GENER ATING STATION P. O. BOX A SAtlATOG A, PENNSYLV ANI A 19464

- (215) 32 71200, EXT. 3000 -

NE"U U' DN

. w m u, tairew m.........,

Docket Hos.- 50-352

...u.........."*a

50-353 License.Nos. NPF-39

-HPF-85 U.S. Nuclear Regulatory Commission ATTH: Cocument Control Desk Washington, DC 20555 4

SUBJECT:

Limerick Generating Station -Units-1 and t-Reply to a Notice of Violation Inspection Report Hos.'50-352/90-28 and 50-353/90-28

Dear Sirs:

ofViolationfor'LimerickGenerating-Station (LGS), Units 1):and2,whichlwasoAttached is contained:in NRC Inspection Report Hos. 50-352/90-28 Land-50-353/90-28, dated Janu ey 14, 1991., This Notice of Violation pertains to;theifailure to adhere ^to stationi procedures and was identified during;an NRL inspection conducted between

-December 1 and 7,.1990, at LGS Units 1 and-2.

The attachment to this letter providesLairestatement of the. violation.:

followed by our response.

If you:have any' questions,-or require additional.

inforration please. contact us.

n.

Very truly yours; r,. M. Leitch

.DCS/rgs Attachment-l cc: T. T. Martie. Administrator, Region I'USNRC :

T..h Xenny,MSNRC Senior ResidentrInspector nLGSi 9102200107 910212,

PDR ADOCK 0500035#

ggo/

y g

PDR w"

f/f Av

~ )..

w..

,. _ gm _

e

,+ <+

r

~ ~,

y 3: gW g, ~ ~^ '

y[

u y;' <,

o

+

a s*

^

y,

, x - w-.. - w yyx 4 - -

t '

cAttachmente w

s.

-...KPage11 ofE3E 4

fInspection'Nos,y50-352/90-28:

N tand 50-353/90,

,0q REPLY TO # NOTICE'0F VIOLATION:

i A

4 3

1 i

^^

Restatement of the Violation During an NRC= insprction conducted on Dechaber>3-7,/1990ia violationif/NRC

' requirements'was, identified. "In accordance with.-tne " General? Statement of hol cyian N ProcedureforNRCEnforcement-Actions,"10CFR1Part2.fAppendix%(1990),Lthet '

"3 violation is listed'belowie W'

~'

hj

'Y n..-...

e A'. ' Technical Specification 6.11L" Radiation-ProtectioOProgram" for bot" mv C, 4

4 requires that procedures:for personnelcradiation protection shall be % paredi _

i consistent lwithithe requirements ofd10'CFRr20 and shall;belapprovedhmaintainedt '

Q and; adhered toifor all operations; involving per @ M a rao1ation exposurs.l...

J,

N Station. health-physicsprocedureHP_-715,lRevisionh0Paragrghi6.3.41statesiin; part, thatLforisurveys performed?on'. outgoing:exclus m use(vehicles; f. n takei' d

radiation reading'asidescribedlin!AttachmentL8;2.". LAttachment!8.2,to:HP-715E '

establishesan'administrativejlimit'of/1;6mres/ hour;inithedri.verfcompa'rtmentl d_

~

n

' ' "V Q 3

(contact ~withrearofcab/ sleeper)? ;

J Contrary to the above,:on.NovembeS8 bl990W th611censeeishipphU rsdibactive W '

,3 material to the:Quadrex Recycling Centerbin'.0ak RidgefTennessee:in a?vehicleL'

-6 there; driver compartment? dose rates M ceeded;theLadrinistrative Aimit: established?

y 4

in~HP-715.c During surjeysiperformed>upon receipt.offthelvehiclelat)Quadrexh y" n

- drMr compartment 3 dose i equivalent; rat es were a determined L to5 be 1425(to : 5' 03

^

U i

mremlaour.

' *n' u,m r@ j g

JThis.is=a-SeverityLevelIVLviol_ationy(SuppleentLIV).;

Q y

m o

1 D

n RESPONSEF, "g

mj p

, Admission.of A11eged 31olation!

~~

m m,

iM' "u

1 e

at

,y 3,. m;

.r q

Philadelphi_aElectric' Company-(PECo); acknowledges l.the'violationn f ',,

j g.

n4 s

2

! Reason for the Violation N

, _ gp i

~

,.. =..

,. a. ~,

v=

.,,_.;1

=while previousisurveys'takenr2 meters:in front:of theitrailer/before(the cab;was; _

J q

n

attached revealedc2 mR/hr.jWh'en attachedWthe 'backsof6the(cakwasLapp'roximately li3N i

u meters;from the frontlof?the trailer D We concluded 7that;thenlow measurementtin; thel H I Ecab resulted from failure of ~the;HP. technician'toiselectlthefproperj scaleDorchisc - #

idetector. JThis: conclusion;isLsupported byfthe fact 3that;the.imeasurements pbtainedtat p 9

c o.

e

, [],_

8 n.

_1 e

r

'd i.

L, w-

, g.;

I

):

s

~

't

?'

"' w '

g;7,

1 g

3 g[ h

? -[ [

I@'

hD.

1

'~

1, i

"[a

' 7 9 M N : A'f)[,

4

.. Wi;I j

. 'f f!A < $ $, '$,1 p:.*

i

_ ig

- Q~@. i %

_ 'f; ", ' %_

94 j

j, y j

h,, l gkr;g, !

w Win S.,

, ! C- +

s--

+4.--*

a t-

.a t

Ati;achment'

, a. -.

. Page 2 cf 3 inspection;Nos. 50-352/90-28.

n and'50-353/.90 ;

Quadrex(3-5mR/hr)(wereapproximately10timesthose.recordedintheLimerick Generatir.g Station LGS) survey, 1

One contributing causal f actor was Nentified in that HP procedure'HP-715,," Surveys in Support of Exclusive Use Radioactive Shipments'and Receipt af.Non Exempt-

' "J Radicactive Packeges," did not requ ae any comparison between lurvey.results'at:the front of the shipping container and survey results in the cab' area. The HP-technician, therefore, did not recognize the disparity. An additional l causal factor-identified was that no.. procedural requirement for, independent. verification of survey results existed. Independent verification may.have offset the potential for human; '

l error. TheLGSdetector(JohnsonExtender 33-0705) was tested-satisfactorily _.

following this event es were the detectors used at Quadrex.-therefore: instrument.

s, malfunction'was eliminated;as_.a causal factor.

Corrective Actions Taken-and Results! Achieved a.

On November 12, 1990, Quadrex's Radiation Safety Officer notified LGS, the State 01%

Tennessee, and the carrier, Scientific Ecology Group (SEG) of tha dose rates 1=,ideL t

the cab ared of the transport vehicle. On Nonmber 12, 1900,-atc1734. hours. LGS =

personnelnotifiedtheNRCiniccordancewith.10CFR50.7?(b)(?)(vi),sincethisle'ent.

v J

resulted :in notification of; the State off Tennessee by!Quadrex. " Additionally, the: HRC:

Resident inspector andLthe: LGS; Plant Manager were notified ofqipotentialiproblem,

with the Radioactive Material shipmentito Quadrex.in Oak 4bige, TN.' On' November 13, 1990, the vendor / supplier of the dosimetry' worn'by-the!SEG1driter verballyire

'110mRquarterlyexposureLto'dateforthefourth'qJarterl(Octhber:-Joecember) ported.

c

!ofx1990' for the driver. LGS personnel, in cooperation with: Quadrex aad SEG: personnel...

estimated the total dose received by the: truck -driver as(a. result of this' shipment!io be 88 mR.

fa Corrective Actions Taken to Prevent Recurrence The HP technician involved was counseled on' the importance of attedion to detail-t when performing surveys. and was appropriately disciplined on' December 11.':1990.

Procedure HP-715 has.been revised te add a note;to the attachment:on which; survey:

readings are recorded indicating (thatt if dose; rates' measured 2; meters from-the'.

of the trailer exceed l'.'6tmR/hr LGS administrative 1.imit).then close attention:

should be paid to dose rates measured in the cab...ThisLw111 aid'in ensuring that?ifi dose rates in the cab exceed the LGS administrative? limit offl.6 mR/hr.the(

appropriate actions will be tcken per procedure HP-715. Direction hasfalso'been added to_ procedureJHP-715 tol require performance 1off a:second! survey hy another-

' individual to-act a Cindependent verification:of initia'l survey results forLall; radwaste shipments except those known'to',havenlow contamination (i.e., clean radwastei and~contaminatedprotective; clothing). An HP Group 'Information1 Notice was' issued 5toi all R personnel.on February 6.L1991,:describingithelevert'and,the related procedural; '

enh'anumenM, and emphasi2ing the importance of attention' to-detad1Lin: processing'

radwasta shipme m.

~

l L

G5 0

.<I

'l 8L i

!M _

2'

...U

% Ji

- N

+ + =.

-,/

1,a

x<

Attachment:

Page 3 of 3-Inspection Nos. 50-352/90-28

)

I and 50-353/90 l i

This procedural non-compliance has-been reviewed, along with other procedural l

non-compliances noted in the inspection report,_as'part of ourJongoing

~

self-assessment process. We will continue to review these types of. issues and-implement corrective actions as'necessary to_further minimize personnel errors.

including those involving procedural:non-compliance.

Date-When full Compliance was Achieved-Full compliance with-associated Regulatory requirements was achieved on November 12,-

1990, at 1734= hours, upon_ completion of allfappropriate notifications. Compliance-has been achieved-upon revision ~of procedure HP-715 and notification of these_ changes-to affected'HP personnel.- This event-is considered to be an isolated occurrence. The counseling / discipline of the involved HP technician, the enhancement of HP-715, and-the performance of an independent verification'of survey.results'are considered

-sufficient corrective measures, e

E 1

1 4,.J.,

,,.m

~~ <

s__,.-.~,

,_.~.,,.,.....Js.

.m

, -*,-