4
3ijl I Nuclr Offi of fort : . d c. . I lato ry si 631 Park A of sia, PA 19406 Sir: r 10, 1982 4410-82-L-D GPU N• •t Post Olf1ce Box 480 Rte 441 South Middletown. Pennsylvania 17057 . 717 944-7621 TELEX 84·2386 Wuter"s Ouect 01al Number: le Isld Stati, it 2 -2) at Li . D-73 t . 50-320 e t 82-035/0lL-0 pl find Lice t 82-035/01L-0 able actor ild S el Indito r 10, !982. is t cti 3.3.3.6 d ied rle r ct 6.9.1.8(b) of Tl Specifits. K// jep Atcts Ì: . L. H. rett, Dector - Office . B. J. yr, o Decto r - Office R12220449 821210 P K 8 P GPU Nuclear Corporat1on IS a subs1d1ary olthe General Pubhc Ullhlles Corporallon

19 ijl I - Idaho National Laboratory · 2013-12-03 · inches HzO on RBS-U'I-6000. (At the time, it le8 expected that there should have had only three (3) to five (5) inches of wter)

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Page 1: 19 ijl I - Idaho National Laboratory · 2013-12-03 · inches HzO on RBS-U'I-6000. (At the time, it le8 expected that there should have had only three (3) to five (5) inches of wter)

19 ijl I Nuclear

Office of Inspection and Enforcement Attn: Mr. Ronald c. Haynes. Director Region I US Nuclear Regulatory Ca!mi.ssion 631 Park Averrue King of Prussia, PA 19406

Dear Sir:

Decal:ber 10, 1982 4410-82-L-0068

GPU Nucle• Corpor•tlon Post Olf1ce Box 480

Route 441 South Middletown. Pennsylvania 17057

. 717 944-7621 TELEX 84·2386 Wuter"s Ouect 01al Number:

11u-ee Mile Island Nuclear Station, \hit 2 ('00-2) Operating License No. DPR-73

Docket No. 50-320 Licensee Event Report 82-035/0lL-0

Attached please find Licensee Event Report 82-035/01L-0 concerni:ng the imperable Reactor Building Su:q> Level Indicator on Noveuber 10, !982.

This event concerns Secticn 3.3.3.6 and is considered reportable under Section 6.9.1.8(b) of the Interim Recovery Technical Specifications.

BKK/SDC/ jep

Attachmnts

CC: Mr. L. H. Barrett, Deputy Program Director - 'D1I Program Office Dr. B. J. Snyder, Progran Director - 'D1I Program Office

8212220449 821210 PDR ADOCK 0:5000320 8 PDR

GPU Nuclear Corporat1on IS a subs1d1ary olthe General Pubhc Ullhlles Corporallon

Page 2: 19 ijl I - Idaho National Laboratory · 2013-12-03 · inches HzO on RBS-U'I-6000. (At the time, it le8 expected that there should have had only three (3) to five (5) inches of wter)

.. RC,OttMiM U. L ttuCUAtt RIGU&.ATOilV e&;li1ii10H C7-77t • .

LICENSEE EVENT REPORT tuo:�£:o668 CONTROL I LOCK: I I 10 CPLIAII "''NT Oft TYPI ALL RIQUIRID IN,OilMAT�ONI

lP IAJ.t;,.!:co�� I2,J(?)!� I ol -1 oL�Lao,.'u!J"ol-1 ol oJ@L4I t.J,,!,IT!}

1IJ0b-J,J®

�'T riiT11 :'!,':! IL ri'llO IS IO IO I O 131210 K!)J 11 11 1 I ol al 2K!)PI2II!'ol al zl(!) ,........-, �at OOC:�tnNUiotll" • • IYINTDATI 7• . " fii'O"TDATl 10

IVINT OUCRimON ANO PAOIAILI CONSEQUINCIS @ [[[!] IAt 1120 hours on Nove!ber 10, 1982, the Reactor Mlding SUm t.eyel Indicator was

[!]!] JObserved to be reading high. Due to this ananaly, the indicator was declared in.?perable.

(IE) (lhls event is considered reportable per Tech Spec 6.9.1.8(b) due to entry in and I

l]li) 1exceeding the tine clock of Soec 3.3.3.6. This event had no effect on tl-.e health and

(]]!] Jsafety of the public.

I!lil oaD L_------------------------------------------------------------------------------------� 7 1 e 10

IYSTltoA CA\JSI CAUSE COM•. VALVE CODE CODE lUI tOOl COMf'()fj(NT COOl lUI CODE IUitODI

II I I@ L.!J@) L!J@) II IN Is IT IR I U11!@ I El@) I XI@ t to , n , tr""' �

� UII"IIO

LYI!ojTV(AII � llf'DIIT I 8 I 2 I fiUI.II(II �

IIOUitjTIAL OCC\JIIIIENC( fiiPD"T "EPD"T 11110. CQOI TYPI

2!•0 13 !Sj L::::J I Ol 1! !L I l=J 3i 27 21 21 � ,, TA!tlloj ACTIQ!oj Qloj PLAI<jT loiETHOO HOUIIIS 22 IUII.IITTIO fO"Iola.UI. IUI',LII"

IIEVISID!oj NO.

L2J ,, cou•o"'c"'T

loiA!ojUFACTUIII" ACTIO.. fUTUIII IHICT IKUTOO¥N � ATTAC:HtlftjT WIIID-4 Pllllt,l( cou•.

m lr.:'ll X I@) I z 1@ I Z I@ I 0 I 0 I o I I IY I@ L!J@) �@) n--'\J'� � � , � r.-' ., ., I ZJ9 19 t9 !@)

CAUSE DESCR.,TION AND CORRECTIVE ACTIONS ® .. .,

III[) tlbis eyent waS belieyed to be caused by a buildup of sludge in the end of the RB Sutp tiliJ Jl.eyel Indicator. The indicator's line was blCMl free with 20 lbs. of pressure. 1m

o:::rn !evaluation of the approorlateness of this type of level indicator is being perfortiVi!d.

CDDD L---------------------------------------------------------------�

[DOD L-------------------------------------------------------------� , I • Wi:\�v •POWEIII OTHIIIIITATUS @ ��\ro�.rv DI&COVtiiiVDISCtunla... ®

£III) lxJ® l...QJ 0 I 0 1@)1 Recovery mode I W@)! Operator observation J I AltiVITY cx::TINT

12 n _. 4l ._

f":"'T:"\fiiUASED Of IIlLI AII AUOUMT Of ACTIVITY ® � l!J ® L!J®I N/A I l I • 10 , ..

PfiiSQtjtiiL U�IJ t:;:.. •

LOCATION Of fiiLIASI ® N/A

10

I 10

10 '-UUillll If.:'::\ TYfl 1!:':\ OI&CfllmON �

[[[D Jo 10 ro ���·��--------------------�N�A�------------------� l I • , 12 jj •

PlfiS(Itj�ojft,. INJUI'. ' Ill � 10

I ,.Wiflll � OIK'IIPTION\!!f

[DG] _o to to J�L-----------------------�N�A�------------------------d l • • " " 10 t.OSS OJ Ofl D•UACI TO fACILITY 14)'

I.'T':1 r:•v:::.. OIICIIIIPTION \::1 � � N/A l I I PUILIC:!'i;I�TY:-'

--C\------; 8;::.2;:"1':":2::':2::':2():-='4� 5::'4� 8=2�12�1 0":"_-

-----------------.�0

f'2"'ii1 1fSU1pQ\!Dtlt"IPTt�� PDR ADOCK 05000320 NRC USE ONLY •

� UW�:----------------8-----·�··-··-----P-DR�-----------� II II 111!11 I I I! J I I ID II It 10•;

'"ONE: (717) 948-8461 : 0

Page 3: 19 ijl I - Idaho National Laboratory · 2013-12-03 · inches HzO on RBS-U'I-6000. (At the time, it le8 expected that there should have had only three (3) to five (5) inches of wter)

..

UamEE EVENr REPCRl' Nf\RRATlVE REPan'

1KI-n lER 82-035/0lL-0

EVmr nuE - NovaJber 10, 1982

Att.ac:!'ant 2 4410-82-L-0068

I. EX1'1mAl'I� OF � At 1120 hours on NovaJber 10, 1982, the Reactor adlding (RB) 5\Jq) Level Indicator le8 observed to be reading high at an indicated twenty-four (24) inches HzO on RBS-U'I-6000. (At the time, it le8 expected that there should have had only three (3) to five (5) inches of wter). M investigation ws initiated to determine the cause of the high reading and correct the situation.

Due to this BI'ICI!Bly, the RB StJq:> Level Indicator le8 declared inoperable. 1hia condition placed the mit in the Action StataDent of Technical Specification 3.3.3.6. At 1920 hours on Noveaber 10, 1982, the eight (8) hour time clock of the Tech Spec Action StataDent le8 exceeded, thus wrranting a pra�pt report pursuant to Section 6.9.1.8(b) of the Recovery Technical Specifications.

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

II. CAmE OF niE �

The cause of this event has been attributed to a builcklp of sludge in the end of the RB SU�p level • s tygon tubing. The level inst:rlmelt is of the bubbler type with its sensing line (tygal tubing) located on the RB basement floor. 'lbe buildup of sludge in the tube is attributed to the recently performed RB decon spraying evolutions in the vicinity of the level indicator's tygal tubing.

III. CIRaMSTANCES �mDING niE � At the time of the occurrence, the thit 2 f4cility le8 in a latg-term cold shutdown state. The reactor decay heat \illls being rermved via loss to aai>i.ent. lbroughout the event there le8 no effect on the Reactor Coolant System or the core.

IV. roRREcriVE ACI'IOOS TAJ<m � TO BE TA..'CEN

lml:ediate

On Novmiler 10, 1982, the cause \iiBS believed to be a plugged line and confirmtorv actions initiated. nlese actions included: • The bubbler pressure was raised to 10 lbs. in an at�t to blow

the tubing clear. However, no change in :indica tim was observed � 10, 1982).

• The bubbler inst:rlmeltation ws checked by setting up a test rig \ofrl.ch ci.Jplicated the Wbbler tube arrangement in a controlled, 1<ncN\ set of cOnditions � 10, 1982).

Page 4: 19 ijl I - Idaho National Laboratory · 2013-12-03 · inches HzO on RBS-U'I-6000. (At the time, it le8 expected that there should have had only three (3) to five (5) inches of wter)

• � Nc:Na1t1er 11, 1982, another attqlt to blOw the line free ws DBde with 20 lba. of preasu:re. '1his dme the level :lndicatim recb:ed fran appradmltely 7 inches to .5 :Inches H20 •

• � lbvalb!r 12, 1982, the level inst:ruDent ws returned to service after a preliminary water balanc:e ealculatim, a visual inspection during an RB entry, and careful tracldng of the inleakage and out-leakage for the RB verified the level :l.Ildicatim ws appropx:iate and operable. '!be preliminary leter balance ealculatial ws verified by a ume detaUed ealculatim perfox:med on Navadler 13, 1982.

ln addition, SSJples wre taken fran the groundwter umitoring stations on NcM!Dber 13, 1982, to determine if sny sitldficant changes had occurred which 'WOUld indicate a Reactor Building leak. These s.q>les and satples taken subsequent to Navadler 13, 1982, have sllCM\ no abncmJal changes in grourdater tritiun activity.

I.ong-Tex:m GPU is evaluating the situation to determine if another type · of level instx:unent 'WOUld be ume appropx:iate ar if sny further corrective action regarding the bubbler is necessary.

V. cx:t11'00ENl' FAIU.m: 'MTA

N/A

� --- .