ML20043C864

Forwards Rept of Local Leakage Rate Test Results for Third Refueling Outage.Leakage Rates of Six Valves Identified as Contributing to Failure of Max Pathway Limit

ML20043C864
Person / Time
Site:	Byron
Issue date:	05/29/1990
From:	Schuster T COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
1029T, NUDOCS 9006060276
Download: ML20043C864 (7)

Text

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'7 m f._ )h Commonwealth Edloon l

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' 1400 Opus Place

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Downers Crove, lilinois 60515 m

May 29, 1990 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn U.S. NRC Document Control Desk

Subject:

Byron Station Unit 1 Failed Local Leakage Rate Test Report NRC Dockrijio. 50-454 References a) January 18, 1989 letter from J.A. Silady to T.E. Murley b) May 3,19891ctter from D.R. Muller to T.J. Kovach

Dear Dr. Murley:

This letter provides a report of the Byron Unit 1 Local Leakage Rate Test (LLRT) results for the third refueling outage of Unit 1.

An Integrated Leakage Rate Test (ILRT) was neither required nor performed during this outage. The intent of this report is to ensure the NRC staff is informed in a timely manner whenever refueling outage LLRT results exceed a cummulative value of 0.6 L (maximum pathway) regardless of whether an ILRT was performed. Reference (a) originally conveyed this reporting methodology to the NRO.

Although the "As Found" 0.6 L max path leakage rate limit was exceeded, a

the "As Found" minimum path, leakage rate total was well within the 0.6 La criteria. The leakage rates of six valves were identified as contributing to the failure of the maximum pathway limit.

Ilowever, none of the failures consisted of two containment isolation valves in series, nor was there an identi,fiabic common mode failure.

After reviewing the 100FR 30.73 reporting requirements as well as the clarification provided in Reference (b), there is no safety significance to the failures and an LER is not required.

The attached special report identifies the components which had a significant leakage; the cause of the failure if identifiable; and the corrective actions taken.

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2-May 29, 1990 l

Dr. T.E. Murley t

i Please contact this office should any additional _information be required.

P Very truly yours,

(*

h f,sT.K. Schuster Nuclear Licensing Administrator-Attachment cet Regional Administrator - RIII P.C. Shemanski - NRR F.A. Maura - RIII Byron Resident Inspector i

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OtVIAft0N REPORT e

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DVR NO.

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Fare Rev 2 h j TITLE OF OtytATION OCCURRtB c2 22 90 0300 Lacal t mah anta feat Failuren M

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$Y$ftM AFFECTE0 l PLANT $TATU$ AT TIE OF EVENT TESTING y,,,,,,

PWDE 1

POWER (1) 0 WORK REQUEST NO.

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l Ot$CRIPTION OF EVENT Durin0 the Unit 1 Refueling Outete (01R03) the following valves f ailed the LLRT: IPS231A, ICC9518.

1$00020,1$0002G.1$0002N and 1$000$0. All components were repaired and tested. The As Left total for all Type B & C tests was within the acceptance criteria.

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g NO POTENTIALLY $1GNIFICANT EVENT PER NSO OIRECTIVE A-07 10CFR50.72 NRC RED PNDE l

l NO R. Dopptoch 02 22-90 NOTIFICAfl0N N t l

l4NOUR Ting netsematatt SUPERVitaa Daft Pant 2l OPERATING ENSIMER'$ CO M NTS e

NON REPORTA6LE EVENT g,g NOTIFICATION 30 DAY REPORTABLE /10CFR REGION !!!

DATE TIME g

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g CECO CORPORAft NOTIFICAfl0N NADE A.I.R. #

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crea ensa0aaff 0FFICER DATE flP

,PRELIMINfAY REPIRT COMPLEft0 A88 REV!tWE0 R. "- ' ins-02-23-90 OPERAT18Fa tur.turre DATE INVE$T!GATION REPORT & RESOLUTION ACCEPTED BY STATION REVitW M NO M

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RESOLUTION APPROVt0 Ale AUTHORIZED FOR Ot$fRIBUTION

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D STATION MuiAGER DATE 3176 (Form 15-52-1) 11/89 a

DOCUMENT 10 (0549t/0068R)

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OtVIATION INVilf!Df!ON REPORT (0!R) g Facility Name PAGE i

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Title wal I**h anta feat Fallaarna EVtWT MTE ata samara arpagt mir

// $EQUENTIAL

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pEBffH MY YEAR l'IA Latif YEAR ff hA_"_a hA aShf e DEMffM MY YEAR

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of 2 21 2 el e el a el 1 el e e 1 3! 4 CONfact Fat fM11 Dia NAgg Trtropnnar ganara AttA CODE A. Jawari l '2alatant fachalcal Staff *~- rvlaar tut. 21M Ai1l1 2l3l4l-l5l4l4l1 CitrLif t GIE ttaf Fon rarns tege naarw? A tier nascatarn tu fuis REPett CAU$t

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TEXT Energy Industry Identification $ystem (E!!$) codes are identitled in the tent as (XX) e l

A.

PLANT CGidllTION1 PRI M TO EVENTt Event Date/ Time e2 22-te /

anna Unit 1 MDOC.5 _ -

tald h* " -

Rn Power _9L.

RCS (AS) Temperature / Pressure 1001 / 0 Pain Unit 2 MODE 1 Pa==> omarattaa Rs Power.255_

RCS (AB) Temperature /Fres,sure Normal Omaratinn 8.

DEstRIPT1831 OF EVENTI During the Unit 1 Refueling Outoge (87903) eueevtion of the Primary Containment (PC) [90) local Leak Rate festa, it was determined that the evere11 assieum pathway containment leakage failed La meet the acceptance of 0.6 L. (277.76 Standard Cubic Feet ser Hour) for the As Fevnd condition. The following components were considered to have unacceptable leakage and/or non-gvantifiable leakage:

While performing serveillance IgVS 6.1.2.0 1.8 section $. a leak rate of >35 Standard Cubic Feet per Hour ($CFM) was recorded for valve IPS231A (Hydrogen Monitor Olscharge Check Valve inboard containment i solation)(1981 IedR 873150 was written to investigate and correct the leakage.

While performing serveillance Ifv$ 6.1.2.0-1.12. section 2. a leak rate of >38 $CFM was recorded for valve ICC9518 (Ceaponent Coeling Pressure Equallaation Valve) (CC). NWR 873195 was written to investigate and correct the leakage.

l While performing surveillance ISYS 6.1.2.0-1.23 section 4. a leak rate of >38 $CFH was recorded for valve 1$00020 ($ team Generator Lower Slowdown Isolation valve) (N!). NWR 9733$7 was written to investigate and correct the leakage.

(0549R/0068R)

OtVIAft^3 I Wtst! '. TION Rtp0Rt itXT CONF!Nutf!0N Farm tev 2 A FACILITY letag BIA =

7 PAGE SE0WENTIAL REVil!ON STA Lall?

YEAR

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E n enn helaar P= = tu d an el a el 1 al a e1a14 eie 2

or oI.

TEAT Energy Industry Identificatten System (t!!$) codes are identified in the tent as (KR)

While perfereing serveillance 10VS 6.1.2.0-1.23 settlen 7. a leak rate of 12 SCFH was recorded for valve 1$00026 (Steam Generator Upper Blowdown Isoletten Valve). NWR 973355 was written to investigate and correct the leakapet While perferoing surveillance 1DV$ 6.1.2.0-1.23. section 0, a leak rate of 20 SCFM was recorded for valve 1$0002H (Steam Generator Lower Slowdown Isolation valve) and valve 1$00090 (Steam Generator blowdown sample toelatten valve). These valves lie in a parallel configuration. NWIt $73364 was written to investigate and correct the leakage for valve 1$0002H and NWR 873366 was written to investigste and correct the leakage for valve IS00050.

A Limiting Conditten for Operation Action Requirement (LC0AA) was not appilcable in Nede 5. All components were repaired and rotested prior to entering Mode d.

Plant condittens remained stable throughout the testing. Operator actions did not effect this event.

l

' NOTE The LLRT test precedure is divided Inte 26 precedures (19VS 6.1.2.0-1.1 threvgh 1.26). SurvelTian 19VS 6.1.2.0-1.25 le the summetten precedure where all penetrations tested are itsted and the 0.6 L Total ManPath Leak Rate Acceptance Criteria is determined for *As Found" and "As left" plant condition.

e C.

Call 1E Of EVENTt The Hydrogen Monitor Olscharge Check Valve failure was indetereinste since the welded body prevented access.

The Component Coeling check valve p1vnger was sticking due to the presence of a foreign metter.

1500020 was feend to have ses11 steam cuts on the seating surfaces. The steam cuts are considered a normal result of the operating enviroveent of the valve.

Valves 1500026, 150002H. and IS00000 had no apparent defects.

D.

RAFETY ANALY1111 The failed isolation valves 1p$231A and ICCg510 have redundant automatic containment feeletten valves whict are aligned in series. These redundant valves passed the As Found test and provided acceptable containment isolation.

The safety conseguence of the steam generator blowdown (seletion valves leakage is etnielsed by the class 15 (selseic and safety related) design of the steam generators and associated piping inside containment.

In a desten basis less of coolant accident, the steam generators and assectated piping provide the containment (seletten fonetten. The toelation valves are not challenged by post accident containment pressure. These isolation valves receive an aute closure signal during a phase A Containment Isolation in order to maintain steam generator inventory, and thus de not perfers a containment Isolation function.

E.

CottECTIVE ACficItit L

Valve IPS231A was cut-out and replaced because the check valve is not serviceable.

Valve ICC9518 was disassembled and cleaned.

l (0549t/00684)

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.fACILifY Imag sta== - a PAar St0UENTIAL ety!$10N ifA Latif YEAa nammes

a. ram naminar r -- statina el a el i el e eIaia ei e 1

or a1 ftRT Energy Industry Identificatten System (t!!$) codes are identified in the tout as (RR)

All steam generator blowdown isoletten valves had their p1ves and seats lapped.

l All components were retested with acceptable results. A Technical Specificatten change regvest has been submitted to ensept the steam generator blowdown containment toeletten valves 1/2 $0002A-H and 1/2 $D00$A.D r

from Appendia J testing for reasons stated in the safety analysis above.

F.

REttatiga EVENTS 1EARCH Am Ah&LY1111 a)

EVENT REARCH fDIR. LEtt 6 1-47-061 Local Leak Rate Test Failure 6-2-43-005 Local Leak Rate feet Failure 6-247-118 Local Leak Rate fest failure 6-1-88-295 Local Leak Rate feet failure 6-2-49-029 Local Leak Rate fest Fallers b)

IIEkliftY SEARCH (OPE 1'a INtil An NMIDS search revealed numerovs fativros industry wide for the Masonellan Internettene) Valve which are used in the steam generator blowdown lines at Dyron. Themejerityofthesefalfuroswere attributed to nores) wear of pivg and seat. OptX reporting revealed nothing applicable to the LLRT valve failures, c) 10 3 A 94A1 Werk History learch revealed the fellowingt ICC9518 was cleaned in 1984 les other work history was found.

IPS231A has failed previews leak rate tests, frond Report 96-006 was issued as a result of the work history.

1$00024 and 180002H have previous work history involving lapping of seat and plug er valve internal replacement due to LLRT fativres. 1$00020 and 1$00090 have no previews history due to LLRT fativre. The steam genereter blowdown valves are subjected to very harsh service. The maintenance history is not considered onceptional in nat'?e. Also, testing of these valves has been roguested for esemptten.

d)

ANALY111 The reevering events search revealed a failure trend for IpS231A. Trend Report 90-006 was issued as a result of this investigation.

G.

COW 0 LENT FAILtRE DATA!

MAltJFACf1RER lapKMcLAftat leDEL ltBSER W G PART lASSER Keretest 3/4= check valve (ICC9518) 3/4 C64 Lfr-6 Nuclear Valve Olvision 3/4" check valve (IPS231A) 16CCB1-004 72278 Masonellan International 2* globe Valve ($D valves) 38-20721 N00109-3-4 (0549R/0068R)

i' ItV!Afl0N 10fvtlfleAfl0N htPORT ftXT CONfleRafl0N ram an 2 6

JACILITY leteE ata --- e paar SESENTIAL REVillge!

ita tadt vtAR avren thainar r -- ta=* tan el a el i el a aiaia ai e a

er eI ftXT Energy Indwelry Identificellen System (t!!$) codet are identified in the test es (ER)

H.

OflER RELAftB p it 96ene

[FFECTIVERE11 REV1 twt 96ene J.

ADbititutiL hatAt a)

Affected Technical Specificettent 3/4.6.1 b)

Procedurest DVS 6.1.2.d-1.1 threvg'n.26 c)

Cause Code AC88R (PS). ROOO (CC). ROSE (30) d)

Egvipment Involvedt Centelneset !seletion Velves e)

Other Local Leak Rate feet Fettures (05494/0068R)