ML19332E761

LER 89-027-00:on 891031,discovered That ESF Bldg Ventilation Radiation Monitors Improperly Declared Out of Svc on 891016 & 25 Due to Low Flow Alarms & Following Repairs.Caused by Administrative deficiency.W/891130 Ltr

ML19332E761
Person / Time
Site:	Millstone
Issue date:	11/30/1989
From:	Conway R, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-027, MP-13786, NUDOCS 8912120091
Download: ML19332E761 (4)

Text

,, b

[].; _li ;

t 'g gg General Offices'Selcen Street Berkn Connecticut I wYsfeNa'sIa'ede'ttNecEc'CoS*ny'

• P o. box 270 L ' ' Norfne*as LEt eNer Spany HARTFORD. CoNNECTIOUT 06414-0270 Northeast Nucioar Energy Company '

(203)665 5000 November 30 1989 MP-13786

',' Re: 10CFR50.73(a)(2)(i)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Reference:

Facility Operating' License No. NPF-49 Docket No. 50-423

- Licensee Event Report 89-027-00 Gentlemen:

i This letter forwards Licensee Event Report 89-027-00 required to be submitted within 'f'

, thirty (30) days pursuant to 10CFR50.73(a)(2)(i), any operation or condition prohibited

_ by the Plant's Technical Specifications.  !

Very truly yours, ,

NORTHEAST NUCLEAR ENERGY COMPANY

.,A Stephe E. Scace Station Superintendent Millstone Nuclear Power Station h

SES/RDC:tp

Attachment:

LER 89-027-00 cc: W. T. Russell, Recion I Administrator W. J. Raymond, S'enior Resident ins 3ector, Millstone Unit Nos.1, 2 and 3 ,"

l D. H. Jaffe, NRC Project Manager, Niillstone Unit No. 3 l

8912120091 891130 PDR ADOCK 05000423 S PDC 1\

NC Form 3th U 6. NUCLEAR REGULATORY COMMISSION APPROVLD OMb NO 3160-044

, (6-80) j EXPIRES' 4 /30/92

+ *

+

E stimatee tvrosn per response to comply with this

. informatsori cohection reousst 60 0 nrs Fo' ware LICENSEE EVENT REPORT (LER). *'"Ce7Eh'a'ndeStElrEE7t$o$"*u^EY2*cien, ne Reguistory commission, Washington; OC 20665. and to tne Paperwork Reduction Project (3160-01(d L Office of Management and Dudget Washington, DC 20603 F ACluTY NAML (H DO At1NOMbth ws 6-^ 9 Millstone Nuclear Power Stauon Unit 3 ol sl ol ol oja l2 l3 1loFl 0l 3 ina m ESF Building Radiation Alonitor Failure Due to Admirmtrative Deficiency E VENT DATE (61 L F A NLIMf4FR (Ci 84FPOR' DATE i7i OTHFA F ACILITIE S INVOLVFD (Bi MONT >' DAY YEAR YEAR MONTH DAY YEAR F ACILil Y NA' vie 6 0.1siofofof I I

~ ~

1 0 3 l .1 8 9 8 l9 0l2l7 0l 0 1l1 3l0 8l 9 olslololol l l OPE R ATING THIS REPORT 15 BEING SUBMITTED PURSUAIF TO THE REOUIREMENTS OF 10 CFR l- (Check one or more of the tonowingut11 7 20 402(b) 20 402(c) 60 73f aH2)Ov1 73 7Hb)

POW R -

20 406taH1Hi) 60.36(c H t ) 60 73ISH2Hvl 73 71(c)

',E,L ' 1l0l0 20 406(aHtuoi

[ 60 3eacu23 _

60.73 cau2x m _

g,LRg 'Sogg'g ,n Text. NRYForm 366A) 20 406(aHtltmi g 60 73(aH2Hu 60 73(aH2HvutHA) 20 406talttlov) 50,73 (a H2 H u) 60 73(aH2HvmHB)

- _ _ r 20 406f airin fivi 60. 73 t a)(2 b DU) 60 73tair2)txi LICENSEE CONT ACT FOR THis LER f t2)

NAMg TELEPHONE NUMBER ARL A COPL Robert D. Conway Senior Engineer, Ext. 5642 2 0l3 4l4l7l-l1l7l9l1 COMPLETE ONE LINE FOR E ACH COMPONFNT F A! LURE DESCRtDED IN TH!s REPORT (135 CAUSE SYSTElv COMPONF NT gh

• d CAUSE SYSTEM COMPONENT NNEk~

l i I I I I I I II I I I I I III I I I l lII I I I SUPPLEMENT AL AEPORT EXPECTED tidi MONTH DAY' YE AR EXPECTED BMiSSION SgAIE C6)

YES ttf vos. comoiste EXPECTED SUBMISSION DATE)  % NO l l l ABSTRACT iumn io 1400 soacet ..... ano,ox,mmeiv tmee, sme-soace iyoewnnen nooi n63 At 2130 on October 31, 1989 while operating in Mode 1 at '1009c power, 557 degrees Fahrenheit and 2250 psia, it was discovered that the Engineered Safeguards Features (ESF) Bundmg Ventilation Radiation Monitor had been improperly declared to be in service due to administrative deficiency, On October 16, 1989 the monitor was placed out of service due to low flow alarms. The appropriate Plant Technical Specification Limiting Condition for Operation (LCO) was entered and all requirements of Action Statements for the LCO were met. The iodme and particulate filter assembly was connected to a temporary pump, and repair activities were iniuated. On October 25, 1989 the monitor was incorrectly declared operable following repairs, l~ wnhout transferring the todme and pcrticulate filter assembly back to the monitor. On October 31,19% the weekly monitor surveillance was performed which removes the I

filter cartridge for analysis and installs a new fiher cartridge. During the surveillance it was discovered that the monitor had not been properly restored on October 25 when repairs were completed. The monitor was immediately and properly returned to service. To prevent recurrence, guidance was provided requiring that a Technical Specification Surveillance be performed prior to declaring a Technical Specification Radiation Monitor operable.

i 1

orm 366 gRj

wsc mm at.c.a v $ westan atoaavorw coassaow awevt D cue to a* ow

, 4-eipi t a ts rao w t stimat.o twoer s+. v.spons.1o comply with this LICENSEE EVENT REPORT (LER) g,mf.n,o'jn ra, eg*c1,*" ';g*5;,6,Q"'4 ,,',*'y48,,

TEXT CONTINUATION .* o v..n.pm.m a .nch u-sam v s wae+.,

o,puio+v comm... ion w ci,ngmn oc tar.t.t. en ine swwo s o.nacuan seo.ei castt-tm on c.o w c.

Manepemem sw twrots Weehmpton Oc Por.03 F AC4lTV NAME O n DOCtJ1NJMbtH W tfDNtVfth Ti l " GL '3' vtAR  % N' Millstone Nuclear Power Station Umt3 og gg og og nya gp g3 ggg Oj : OF o g ;l "! 0l0 0l3

- pmo.. .a. .. .. ... .. -,,.n., unc o- . , o n I. Detenntion n! Event At 0130 M October 31, 1959 while operatmp m Mode 1 at 100r poacr. $$"' degrees Fahrenheit and 20$0 psia, it was dncmcred that the Engineered Safety Features (ESF) Duilding Ventilanon Radiation Monitor had been improperly declared to be in service due to admmistrauve deficiency.

On October 16,19b9 the monitor was placed out of service due to low flow alarms. The appropriate Plant Technical Specihcation Limitmp Condition for Operation (LCO) was entered and all requirements of Acuon Statements for the LCO were met.

The iodme and paruculate filter assembl3 was connected to a temporary pump, and repair activities were initiated. On October 23, 1969 the weekly suncillance was imtiated wh:ch remoses the iodine and particulate liher cartridge for ant. lysis and mst ills a new filter cartndre. Smce the fiher assembly was connected m the temporar) pump, and the monitor was still out of service, the restarauon steps of the surveillance were not completed. Followmp repairs, the temporary sample pump and fiher assembly were remosed for fmal testmp. On October 0$,1989 the monitor was mcorrectly declared operable when repairs and tests were completed, but without transfernnp the iodme and paruculate hiter assembly from the temporary pump to the momtor. On October 31, 1960 the weekt) Suncillance was apam performed which removes the hlter cartridge for analysis and instalb a new filter cartndre. Durmy the surveillance it dncovered that the morntor had not been properly restored on October $ when repairs were completed. The monitor was immediately and properly returned to service. No other immediate scuons were reqmred in response to this event,

11. Cntae of Event Root cause of the event was acimmistrative dehciency. There was inadequate administrative guidance on the requirements for restorms radiation monitors to operable statuL As a result, the radiutten monitor was prematucely declared operable on October 25, based on the completed work pach te. Ambiguout communicauon between departments contributed to the esent. +

111. Annh sit of Every This event is reportable under 10CFR50.73(a)(2)(i), any operauon or conoition prohibited by the Plaat's Technical Specihcations. Based on previous samples cohected from the iodme and particulate hhers, the less than detectable paseous acuvny samples collected every 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for the prior eight days, and the ab>cnce of am symhcant plant power changes, there were no radioacuve discharpes from the ESF Buildmp ventilation system. Pubhc health and safety were therefore not ugnificantly affected.

IV, Corrective Action Upon discovery, the monitor was immediately returned to service. To prevent recurrence, a procedure will be deseloped covenny restoration of radiation monitors, including performance of Technical Specificauon Suneillances where apphcable. This event has been discussed with all affected departments and mt.nm guidance has been provided to personnel uhile the procedure is being developed.

WRC sorm 3f4A 4 691 L

i >

i

. +c +wm ma v 6 wucaan ntaustosv ccesso.* m w doovt.No usa-pua

. 1s+897 F A8%Es a 3a 92 Istimai.o two.$ w t.spons, to comply w*th this

'

• St 60 0 '"**'$

LICENSEE EVENT REPORT (LER) com"m.ni 'r**'* co"*

i 'n*g'too".n estimet,'"se it. 4.was '

TEXT CONTINUATION .no n un v s. N  :

in.

s.p 5ivveco.,m w s.ep.

www s cacion m,.sen.

pro.

e.p.m.ni w w ,,ncionvoc enen n

tasss e .ew n-s30, u.n.p.m.ni .no sane w .n. :neon inso-on=

oc c:+oa> onic.o ie F ACW Y NAM! o p DoCNET NJMbth O t Fm Wutsrp 4 ' *

• GI (J i vi An elma.mm. g i Millstone Nuclear Power Station U"" 3 ~ ~

ol 6l 0l 0l ol4 l2 l3 8l4 0l2l7 0l0 0l 3 OF 0l3 nx1 <n me. so.r. ,. r.a m.o v e oo,w.. usic so m ma si or, Y. .Additionn) lhformntion Three similar esents of failure to propert) adhere to the requirementi, of Technical Specification 3.3,3.10 are described in Licensee Esent Repons b6-06-00, 67-46-00 and 86-17-00. While these esentt are similar in their relation to the Technical Specihceuon, there were significant differences m the sequence of actions durmy each esent. The correctne actions were adequate to prevent recurrence of the same esents, but due to the unique circumstances in each case, these previous corrective actions could not have prevented this event.

Ellc codes SvMems Control Complex Environmental Control System - V1 Radiation Monitortnp System - Il comnonenn Rachation Monitor - MON j i

t r

i l

i I

1 l Nnc Form 306 A is-W) l

_ _ ___ _