U Hucie orporationPost Off Box 480Route-441 SouthMiddletown, Pennsylvania 17057717 944-7621TELEX 84-2386Writers Direct Dial Number

ER

LER 11

ULM DATE 2.3.....01a12.:

II PD MD DATE ,8734

CUD DATE 411■1.11.010041000•1•001..0.1111•1•1•1.

Office of Inspection and EnforcementAttn: Mr: Thomas E. Nutley

Regional AdministratorRegion IUS Nuclear Regulatory Commission431 Park AvenueKing of Prussia, PA 19406

Dear Sir:

Attachments

Nuclear.

Three Mile Island Nuclear Station, Unit 2 (TMI-2)Operating License No. DM-73

. Docket No. 50-320 Licensee Event Report 83-035/99X-0

Attached please find Licensee Event Report 83-035/99X-0 concerning the,failure of NSA Ultra Filters on July 20, 1983.

Please note, under the applicable Technical. Specifications at the timeof the failure, this is not a reportable event since no specificationswere violated. However, given the circumstances of the event, we arereporting this event as a special event.

Sincerely,

/s/ J. J. Barton for

B. K. KangaDirector, TMI-2

CC: Mr. L. H. Barrett, Deputy Program Director - TMI Program OfficeDr. B. J. Snyder, Program Director -.TMI Program Office

GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

NAME OF PREPARER Russ Wells

.. ,. ..U.& NUCLEAR REGULATORY COMMISSION

0473 ')

LICENSEE EVENT REPORT- Attachment 1'

4410-83—L-0177

CONTROL BLOCK: I 1 1 1 1 1 10 PLEASE PRINT OR TYPE ALL REQUIRED INFORSAATiOPQ

PIAIT1M 1'12101n In 1- in In In In In 1_ 0 1 0 1®L4 li i ill 11 1

B 9 lowing Woe 1011 IS LICENSE WAWA SO 17 T MI

CON'T o L Ot015101 0 i Oi A 21 n0 O 1 01 R 1 1 I 6 I RN 1®SOURCE

Air Techniques Q-127 respirator filter testing device at TM'. The filters were sent

to MSA for further testing. 50 additional NSA filters were tested during the week of I

L. July 25, 1983. Three (3) failures were found; these were sent to Air Techniques.

I Test results from ?SSA and Air Techniques confirmed TMI's readings. This event is

vv 1 not reportable pursuant to TMI's Technical Specifications.

$0SYSTEM CAUSE CAUSE COMP. VALVECODE CODE SUS CODE COMPONENT CODE SUB CODE $'JICODE

Lzizi© LUC) )11_18 ixixixIxtxtx18 1de (o®• 10 11 12 13 isSE QUENTIAL OCCURRENCE REPORT REVISION

Lf .pt o VENT YEAR REPORT N0. CCOE TOE NO.

PRQ...9 REPOISE P

RT I 8 1 31A 21 27 .1=j- 1 ni 1.‹.) 19 1 927 1 L.0-132ACTION FUTURE EFF CT SHUTDOWN ATTACHMENT NPR 0-4 PRIME COm•. COMPONENTTAKEN ACTION ON PLANT METHOD HOURS 0 SUBMITTED PORN I.LIII. SUPPLIERR MANUFACTURE .1

X va ky JO X121 i n 1 n I n 1 n 1 Lyj 0 LAJO W® 1 It 1 3 I 1 I sle40 41 42 43 64

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 0(Based on a discussion with the filter manufacturer. the rAnae of the event limners to

1be due to an adhesive separation between the filter media and the filter base. Only

1 MSA ultra filters which have been tested and found acceptable will be issued for ficld I

Ott? Luse.. This LER will be updated upon receipt of formal documentation from the

manufacturer, if necessary.

ElSTATUS % POWER OTHER STATUS 30

FACIttTY

LIU 0 101 010c) Recovery MadeSIARICTI9LEYAs1TY„ ocC°1:11TELERTAsE 12 1m.3 toverr or

ACTIVITY 0

"CAI*" OF RELEASE 0N/A j - N/A Ups We ® 10 11

PERSONNEL EXPOSURESNUMBER TYPE "SCRIPT/C.1 CDo o o ®Z C) N/A

I I 11.4ja 13PERSONNEL IES nDER DESCRIPTION

BO 1010 10 0 N/A • • 11 12

Loss or co DAMAGE T O FACILITY nTYPE ECRIPTION

OD 1 Z 42 N/ANRC USE ONLY

DOCK ET NUMBERREPORT DATE SOEVENT DATE

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES ®I On July 20, 1983, 36 Mine Safety Appliances (MSA) Ultra Filters were 4iscoveud to

have penetration levels in excess of the allowable 0.03% based on results from the

Attachment 24410-83-L-0177

LER 83-035/99X-0EVENT DATE - July 20, 1983

I. EXPLANATION OF THE OCCURRENCE

The following event is not reportable pursuant to TMI-2's InterimRecovery Technical Specifications; however, given the nature of theevent, CPUNC is reporting this event as a special report.

During the week of July 18, 1983, an Air Techniques Q-127 respiratorfilter testing device was placed into operation at TMI. Initialfilter testing revealed satisfactory test results for all makes/types of filters utilized with the exception of the Mine SafetyAppliances (NSA) ultra filter. A sample of 144 NSA ultra filters,manufactured during the period of May - July, 1981, were tested onJuly 20, 1983. Of the 144 filters tested, 36 (25 percent) exhibitedpenetration levels in excess of the allowable 0.03 percent. The0.03 percent corresponds to a 99.97 percent removal efficiency of thermallygenerated 0.3 um dioctyl phtalate (DOP). The 36 filters of concern weresent to the MSA factory for testing and evaluation on July 22, 1983.Subsequently, test results from TMI were confirmed by NSA on August 9,1983.

During the week of July 25, 1983, 50 additional NSA ultra filters,manufactured during the May - July, 1981, timeframe, were tested withonly 3 failures observed. Of these 50 filters, 20 (including the 3failures) were sent t.) the respirator filter testing machine manufacturer,Air Techniques Inc., on August 3, 1983, in order to verify the accuracyof the recently installed filter testing device. At this time, testresults from NSA had not yet been received. The leakage readingsobserved at Air Techniques confirmed TMI's leakage readings (i.e.,the average difference of TMI's readings minus the average differenceof Air Techniques' readings was less than 0.001 percent). Ten ofthe 20 filters tested at Unit 2 and Air Techniques (including the 3failures) were delivered to the NRC on August 4, 1983, for additionaltesting at Los Alamos Scientific Laboratory (LASL). Test results fromLASL were consistent with those of TMI and Air Techniques.

Leakage rates for the 39 defective filters ranged between 0.03 percentto 1.148 percent with the majority in the range of 0.03 percent and0.06 percent.

Additionally, an unopened case of 36 NSA ultra filters manufacturedduring the May - July, 1981, timeframe were delivered to the NRC onJuly 29, 1983, for testing at LASL. Test results received from LASLindicated no failures in this group.

TMI-1 vas advised of this event due to the fact that NSA ultra filtersare used by Unit 1 and Unit 2 personnel.

Based on a discussion with the filter manufacturer, the cause of thefailures is believed to be due to an adhesive separation between the

filter media and the filter base, thereby resulting in bypassing ofthe filter media.,

III. CIRCUMSTANCES SURROUNDING THE OCCURRENCE

Prior to the installation of the respirator filter testing device at

TNT, manufacturer tested filters were issued to personnel anddiscarded after use. The function of the filter testing device is totest each filter after use ^ad reissue those which do not exceed the

allowable penetration criteria, thus reducing the amount of filterreplacements.

IV. CORRECTIVE ACTIONS TAKEN OR TO BE TAKEN

Immediate

Only ?SSA ultra filters which have been tested and found acceptablewill be issued for field use in either Unit 1 or Unit 2.

This report will be updated, if necessary, upon receipt of formal documentationfrom the filter manufacturer concerning this event.

Ultra filter - Mine Safety Applicances(Part No. 464807)

CAUSE OF THE OCCURRENCE

V. COMPONENT FAILURE DATA

Mr. E. L. Blake, Jr. Mr. Thomas Gerusky, DirectorShaw, Pittman, Potts & Trowbridge Bureau of Radiation Protection1800 H Street, NW PA Department of EnvironmentalWashington, DC 20036. Resources

Fulton National Bank BuildingHarrisburg, PA 17120

Hr. George KulynychBabcock ani Wilcox, Inc.P.O. Box 1260Lynchburg, VA 24505

American Nuclear InsurersAttn: Mr. P. R. FoxThe Exchange, Suite 245270 Farmington AvenueFarminet 1. CT 06032

Hr. T. F. Hartley, Jr.Mr. Willis Bixby Marsh and McLennan, Inc.Department of Energy (DOE) 1221 Avenue of the AmericasBuilding 400 - THI New York, NY 10020

Mr. Harold BurtonEG&GBuilding 400 - THI

Di. Steven Long, DirectorPower Plant Siting ProgramDepartment of Natural ResourcesTawes State Office, Building B-3'580 Taylor AvenueAnnnapolis, MD 21401

LER's Only

MO Records CenterSuite 15001100 Circle 75 ParkwayAtlanta, GA 30339

US Nuclear Regulatory Commissionc/0 Document Management BranchWashington, DC 20555

P. WalshTechnical FunctionsGPU Parsippany - Cherry Hill Building

■•• 41. S5 • 4,

GPU Nuclear CorporationPost Office Box 480Route 441 SouthMiddletown. Pennsylvania 17057-01917'7 944-7621

-ELEX 84.2386

Writers Direct Dial number:

November 30, 19834410-83-L-0280

Office of Inspection and EnforcementAttn: Dr. T. E. Murley

Regional AdministratorUS Nuclear Regulatory CommissionRegion I631 Park AvenueKing of Prussia, PA 19406

Dear Sir:

Three Mile Isle. -1d Nuclear Station, Unit 2 (TMI-2)Operaciag License No. DPK-3

Docket No. 50-320Licensec Event Report 82-035/01L-1

Attached please find revised Licensee Event Report 82-035:31L-Jconcerning the inoperable Reactor Puilding Sump Level Indicatoron November 10, 1982.

This event concerns Sec:ion 3.3.3.6 an0 is considered rerort-able under Section 6.9.1.8() of the Interim Re:..overy Technical.Specificatiors.

Sincerely,

/s/ B. K. Kanga

B. K. KangaDirector, TMI-2

BKK/RDW/jep

Attachment

CC: Mr. L. H. Barrett, Deputy Program Director - TMI Program OfficeDr. B. J. Snyder. Program Director - TMI Program Office

GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

IIRCPORMEMI UPDATE REPORT - Previous Report 12/10/82 U. S NUCLEAR REGULATORY COMMISSION(1•771 Att achment 1

LICENSEE EVENT REPORT 4410-83-L-0280CONTROL ',LOCK ti III I 10 PLEASE PRINT OR TYPE ALL REOUIRZ, INFORMATION)

1 0 1 1 11p i A lTI m ITI 2)Cto_i of -1 ol of al 01 01 -!_d_dq4 I I I 1 ItiJ• • LICENSEE C.1101 1• IS LICENSE Nuuse• LICENSE TYPE JO SI 1•4

COPCTFri 01 5 0 0 0 3 2 L11113101311Rf NAT

01 peck ET 011./14•1.14 EYE MT DATE 74 7S REPORT DATE

0

0 II

EVENT DESCRIPTION AND PRODAILE CONSEQUENCES'At 1120 hours on November 10, q82, the Reactor Building SUMD Level

.ndicator was observed to be readin; hi h. Due to this rnmaly, the __J

ors ;indicator was declared inoperable. This event is considered reportable!

!per Tech Sp ec 6.9.1.8(b) due to entry in and exceeding the timeclock I

lof Spec 3 3 1_6. This event had no effect on the health and safety of I

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CAUSE DESCRIPTION ANC) CORR:CT1VE ACT I ONS 0(This event wa. believed to be caused by a buildup of sludg q in the end

/of the RB Sump Level Indicator. The indicator's line was blown free

!with 20 lbs. of pressure. An evaluation of the RB Sump Level Indicator,

'was perfor–ed and it was determined to be satisfactory. Additionally,

Ithe 5u7 Level Indicator will be blown down monthly to prevent clogginq•

OT .E• ST ATuS 0 0,4E04114YMt T.400 OPc•scov DESCIT,►1.7.IN

' Operltor observation 7

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Attachment 24410-83-L-0280'

LER 82-035/01L-1EVENT DATE - November 10, 1982

EXPLANATION OF THE OCCURRENCE

At 1120 hours on November 10, 1982, the Reactor Building (RB)Sump Level Indicator was observed to be reading high at anindicated twenty-four (24) inches 1120 on RBS-LTI-6000. (Atthe time, it was expected that there should have only beenthree to five inches of water.) An investigat:m1 was initiated .to d-termine the cause of the. high reading and correct thesituation.

Due to this anomaly, the RB Sump Level Indicator was declaredinoperable. This condition pla'ed the unit in the ActionStatement of Technical Specification 3.3.3.6. At 1920 hourson November 10, 1982, the eight hour timeclock of the TechSpec Action Statement was exceeded, thus warranting a promptreport pursuant to Section 6.9.1.8(b) of the Recovery TechnicalSpecifications.

The RB Sump Level Indication was returned to service at 1900hours on November 12, 1982.

II. CAUSE OF THE OCCURRENCE

The cause of this event has been attributed to a buildu1 ofsludge in the end of the 'B Sump typnn tubing. Thelevel instrument is of the bubbler type with its sensing line(tygon tubing) located on the RB basement floor. The built'upof sludge in the tube is attributed to the recently performedRB decon spraying evolutions in the vicinity of the levelindicator's tygon tubing.

III. Cl4CUMSTANCES SURROUNDING; THE OCCURRENCE

At the time of the occurrence, the Unit 2 facility was in a longtem cold shutdown state. The reactor decay heat was beingremoved via loss to ambient. Throughout the event there was noeffect on the Reactor Coolant System or the core.

IV. CORRECTIVE ACTIONS TAKEN OR TO BE TAKEN

immediate - On Novembr: 10, 1982, the cause was believed to be aplugged line and confirmatory actions were initiated.These actions incl..Ided:

° The bubbler pressure was raised to 10 lbs. in anattempt to blow the tubing clear. However, nochange in indication was observed (November 10,1982).

o The bubbler instrumentation was checked bysetting np a test rig which duplicated thebubbler tube arrangement in a controlled,known set of conditions (November 10, 1982).

o Another attempt to blow the line free was madewith 20 lbs. of pressure. This time the levelindication reduced from approximately 7 inchesto .5 inches H20 (November 10, 1982).

o On November 12, 1982, the level instrument wasreturned to service after a preliminary waterbalance calculation, a visual inspection duringan RB entry, and careful tracking of the inleakageand outleakage for the RB verified the levelindication was approviPte and operable. Thepreliminary water balance calculation wasverified by a more detailed calculation performedon November 13, 1982.

In addition, samples were ta! •en from the groundwatermonitoring stations on November 13, 1982, to determineif any significant changes had occurred which wouldindizate a Reactor Building leak. These samples andsamples taken subsequent to November 13, 1962, haveshown no abno7mal changes in groundwater tritiumactivity.

Long-;ern: - GPUNC has monitored the RB Sump Level bubbler systemfor approximately one year. The results of thismonitoring have demonstrated that the presentinstallation is providing reliable RB Sump waterlevel indication. GPUNC has, thErefore, determinedthat the present system is satisfactory

In order to alleviate occurrences of this reportableevent, the bubbler line will be blown down once amonth in order to p revent clogging of the RB Sumplevel's tygon tubing.

ot,

EG&GAttn: Mr. Harold BvrtonBuilding 400 .- TMI

LER's Only

TMI-2 bcc list'(external distribution`'

Shaw, Pittman, Potts 6 Trowbridge Bureau of Radiation ProtectionAttn: Mr. E. L. Blake PA Department of Environmental1800 N S • reet, NW ResourcesWashing on, DC 20036 Attn: 4Mr. Thomas Gerusky, Director

Fulton National Bank BuildingHarrisburg, PA 17120

Babcock and Wilcox, Inc.Attn: Mr. George KulynychP.O. Box 1260 Americzo Nuclear InsurersLynchb4.4, VA 24505 Attn: Mr. P. R. Fox

The Exchange, Suite 245270 Farmington Avenue

US Nuclear Regulatory Ccmmission Farmington, CT 06032c/o Document Management BranchWashington, DC 20555

Cover Letter Only

Department of :aergy (DOE)

Marsh and McLennan, Inc.Attn: Mi. Willis 3ixby

Attn: Mr. T. F. Hartley, Ir.Building 400 - TMI

1221 Avenue of the AmericasNew York, NY 10020

INPO Records CenterSuite 1500

Department of Natural Resources 1100 Circle 75 ParkwayPower Plant Siting Program Atlanta, GA 30339Attn: Dr. Steven Long, DirectorTAWS Stv.e Office, Building B-3580 Taylor Ave;:ue GPUNC Prrsippany - Cherry Hill BuildingAnnapolis, MD 21401 Attn: Mr. P. Walsh

Technical Functions Department