05000461/LER-2019-004, Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications

From kanterella
(Redirected from ML19347A427)
Jump to navigation Jump to search
Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications
ML19347A427
Person / Time
Site: Clinton Constellation icon.png
Issue date: 11/29/2019
From: Chalmers T
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SRRS 5A.108, U-604517 LER 2019-004-00
Download: ML19347A427 (4)
v • d • e


LER-2019-004, Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)
4612019004R00 - NRC Website
v • d • e

text

Clinton Power Statlon 8401 Power Road.

Clinton, IL 61727 U-604517 Novembe~ 29, 2019 U.S. Nuclear Regulatory Commission

.AITN: Document Control Desk Washington, D.C. 20555-0001 Clinton.Pow~r Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Subject:' Licensee Ev~nt Report 2019-004-00

. - Exelon*Generafion~

10 CFR 50.73 SRRS 5A.108 Enclosed is Licensee Event Report (LER) 2019-004-00:* Safety Relief Valve Wiring Issue Results in C_ondition Pro~ibited by Technical Spec/f[~ations. This report i.s being submitt~d.jn*p.ccordance with'the i-E?quirements.of 10 CFR q0.73.

There are no reg~latory commitments contained in this report:

Should. you 'have:ariy questions concerning this report, please contp.ct Mr. Dale Shelton, Regulatory Assurance Manag~r, at (217) 937-2800.

R1;3spectfully, Thomas D.

mers Site Vice Pwsident

  • Clinton *Power Station

,r Attachrpent:

  • Licensee Event Report 2019.-004-00 cc:

Regional Admi,nistrator - Region 111

  • -. l

NRCFORM 366 (04-2018)

US. NUCLEAR REG.UL:ATORY COMMISSION

~PROVED BY OMB~ NO. 3160-0104 EXPIRES: 03/3112020

'.. ~""4"<.

~

~

.*... ~_

.LICENSEE EVE;t;JT REPORT (LER) * *

~

bllllln per f""l'<me 1i:J COIT!lf/ wlfl tiJ,s merd!toly cobctlc<1 raq~ 80* oo,.n R"!)Or\\oo IBums leamod 1118 ""°'1>0!"led nkl llo 11:0fllllg pnlC8Sa ml fed bod< kl nduJtry

  • Send COITJ1l&"G regaidng burdan -

to Dl0 lrbmatton Sem:e< 8rard, [T-2 f'.13), Us* Nt.dw Rlgu!MJ<y Corrmsmn. W...hrlgm; DC 20555-0001, or t1f 8-ITlllll 1:>,

lnlocolocll A IIO t>'Ct O rrc rp,, ard I:> Ill D 1111< Ol!a:ar, Ofta of hformalJJo llfld AIQIJ!!my fJi!n. M:08-10202, (3150-0104), Oloce of M,mgomeot mil El<Jo,jet, ~.

DC 20503 W

~ ' IJ100/\\I usld I:), ""'°'"

M n/onna.:rl

coltco, clots rol

~

a cu~ vald 0MB coo1ro1' rarber,, ha Mic rTlll)' rol conw:t Of *POfl!Or: and a p<non

" no( fBl1Jled kl r-..pord to, tie nfolTM!nn cohcllJ1

. f' II I:

~

r.:1

~~:

p (See Page 2 for reqy,red number 'of d1grts/characters for' each block)

(See NUREG-1022, R 3 ior mstruct10n and guidance for completlng this form http ljwffw,nrc gov/readmg-rru'doc-col~ect10ns/nuregs/stafl/sr1022/r3/).

1. Facility ~~11:ne Clinton_Powed=1tation, Unit *1
2. Docket Number 05000461
4. 'Tltle 3.Page

.1

, OF 3

Safety' Relief Valve Wiring Issue Results in Condition_ Prohib-ited by Technical Specif;cations

5. Event Date Moolh Dar, ;, ~ear Year
6. LEA Number* * - * -

I Sequen!lal Number I Rev No 10 02 2019 2019 004 00 7: Repo_r:t Date

  • MontJi

_

  • Day y-12 02

?019 Fac1hty Name FBCilrty Nama a. Other Facilltles.lnvolved Docket Number 05000 Docket Number 05000

9. Operating Mode
11. This Rep~rt,ls Subml\\ted Pursuant to the Requirements of 10 CF~§: (CIJ9i:k all that apply) 5 O* 20 2201{d)

D 20 2203{a)(3)(11)

'D 50 73,(a)(2)(1,Q(B) 0 50 73(a)(2j(~11)(Bj D 20 2203(a)(1J.

D 20 2203{aJt4J D so.73(a)(2Jt'i11i

- 0' 50 73(a)(2)(1x)(A)
  • D 20 2203{a)(2){,)
  • o* 50 36{c)(1)(1)(A)

D 50 73(a)(2)(1VH:4i 0 5~ 73(a)(2)(x)..

10. 'Power,Level

, tr ;o 2203{a)(2){11)

,',. :o* 50 36(c)(1)(11)(A) 0 50 73(a)(2){~)(A) ;

  • D 20 g2ro(aJi2it,11J D 59 38{c)l2) 0 50 73(a)(2){v)(B)

D 20 2203{a)(2){1v)

.D *so 46{a){3){11) 0 50 73(a)(2)(v)(G)

D 73 n(a)(1)..

tJ 20 2203{a)(2){v)

[J 50 73{a)(W1)(A) 0 50 73(a)(~)(v)(D)

D. 73 ~1(a)(2)(,J 000 D. 20 2203{a)(2J(~*l [8j 50 73(a)(2){1)(B) tJ !3 n(a){2)(11).

  • 0 Other (Specify In Abstract below or I~ N'Rc F~rm 36!:,A).
12. Llcen11~.Contact for this LEA Licensee Contact *

. Mr. Dale Shelton, At3gulatory Assurance.Manager I

Tel~phone Numl_)er (lnclyde ~rea Code) *

(217) 937-'2800

13. Co.mplete One Lin~ fqr eai:h.Co~ponent Fallw_e Des~rlbed In 'this Report

Cause

Syst""'

Component MenufactLa'er

' Reportable io' JcES : /

Cauoe' System

~onant RltpOrtable io ICES

14. Supplemenml Report Expected Month Day Year 0 Yes (If yes; 'complete 15. ~xpected Si.Jbml~1on Date) D 'No:.

~5. Exp~cted Submission Date

' - 01 '

31 2020 Ab_stract (Limit to 1400 spaces, 1.e, approXJmately.14:slngle-spaced typewntten,lines)

On bctober*2, 2019, at 02QO CDT, at 0% power,with the unit shutdown for r~fuehng outage C1 R1~. while performing*: -*

Safety Relief Valve (SRV) testing, *SRV 1 B21-F041.B did r:1ot open upon demand u~ing the Division i Main Control R66m (MCR)' switch. Further,inv~stigation identified that' the Division 1 'MGR switch for SRV 1 B21-F041 B opened SRV 1821-

. FQ51 Band the Divis1on *1' MGR switch for S,RV 1 B21-F051 B open'ed SRV 1 B21-F041 B. Initial investigation determined this.conditiori was* a D'ivision 1 SR\\/ wiring issue that occurre*d during refuehpg*outage C1H17 in May 2017. The Division 1 SRVJ B2Hro41B and SRV 1 B~h-F051B wiring was corrected and a post-maintenance test completed. The cause of this.condition is t:Jr;ider investigation. *The causal factors that resulted in the conditiont associated corrective-actions, and s*~'fety consequence? ~ill be provided in a revision to this Licensee Event Report (LE(i)'.' This conditiqn rer:i.ae~ed the Automatic Depressuriiati6n Syst~m (ADS) function for SRV 1 B21-F041 B inoperable since March 2017. As a result;_

  • Techrnq91-S:pecifications Limiting _Condition for Operation 3.5.1, Emergency Core Coohhg System - Operating, Action :E

{One ADS valve inoperp-ble), which requires an.inope'rable ADS va,lve be restored within 14 days,, was riot.rn~t.

, T~erefore, the condition d~scribed in t~1s,LER is reportable.under 10 CFR 50.73(a)(2)(iHB), any operation cir condition which 'h'.as p~ohibited by the.plant's Technical Specifications.

NRC FORM 366 (04-2018)

PLANT AND SYSTEMIOENTIFICATION

General Electric**-:- 89iling WaterHeac_tor, 3473 Megawatts Thermal Rated Core Power Energy_ Industry ldentific~tion System (EIIS) codes are identifi~d in text as [XX].

EVENT.IDENTI FICA Tl ON Safety Reljef Va.Ive Wirihg Issue Results in *condition ProhlbitJd by Technical *specifications A.

Plant Operating :-cori~itions Before the Eve:nt Unit: 1 Mode: 5 Everit Date, Octobe.r 2, 20'19 Mode Name: Refuelirrn

  • B.

. Description of Ever,t,

Event,Tlme: 0200 Reactor Rower: ooo

, On October 2, 2019, at 0_200 CDT, at 0% power withJhe urit shutdOY'{ll for refueling outag~ C1H19, while perfbrmir)g-Safety Reli~f,'Vq!ve [RV] (SRV).te~tjng, SRV 1.S21-F041 H did not open upon*

deniand using the Division 1 Main Cciritr6f Room *(MCR) switch [HS]. Further-, investHJation identif1ed that*the Division 1 MCR switc;h f6~ SRV 1 szf-F04.1,B opEined SR\\/ 1821-FOS 1 B and :the,Division *1.

MCR switct1.tor: SRV 1821-f05H3 opened SRV *182t-F041 B. The Division 2 MCR sw.itches-fcir SRV 182l-F041 Band :SRV 1 B21-F051'Ei"operated correctly. The.affe~te*d SRVs ~re adjacent to each other. ii) 'the Reactor Dryw~II.

C.

Cause of the. EvenJ, Initial investigation identified a Divi,sion 1 SRV wiringj,ssue that occurred during refueling dutage C1A17 in M~y.:2pf7. A causal evaluatior:i for this condition is in progress. T~e causal.factors 'that

~esult~d in the conqiti9n :c1:nd the assocJated-corrective ac~iqns wiU.be provided in a revision to this.,,

Licer'see Eyerit Report" (LEA).

D.

Safety Cons.equences SRV 1821-FQS:1 B has a Safety/Relief (S/R) function and a Low-Low Set.(LLS) functio.n. SRV.1821-f0418 has an SiR ~unction ahd a'f1 ACliomati_c Oepressuri2;atiori System (ADS) functJon. The LLS Relief Function is armed. upon relief.actuation.of an S/R valve a'rid *will cause a greater magnitude blowdowi,. (in the relief mode} for specified 'S/R v~lves and a si:ibsequent cyci'rng of a single LLS..

' Page _2_ of __L

. _:\\..

I '

  • __,

I'.

.. ! ? ~* **

!I I

1. FAC)CITY NAME:
  • 2;.00CKJ:TNi:iMBER

. -3. 't.:.ER NUMBl;R ~

Clinton Power Station, Uriit 1 *

~

1' I

>/ )

05000461

. YEAR

,s*e9u~i:.,.

  • .NUMBER

/_.

(

2Q1.9 004

~'....

~ ~' :

REV

'N9. '

NAFt'R*ATIVE

',. valve: The L~~ an,d :SIR functiorii ~~*re:not af{~¢tW by thjs con~,ition. -~ow~v*~r; '.c!~l to :~~.umul~tor volume.design reqi:ijremerits for the,Abs*.. sR\\(, this copditio'n'i~n~erea tl:ie'J\\:QS f1,niptiohJpr, SRV * :*.:

. 1 s2*1-FOfl ~ *inpp~rable sine*ei tyi~y*_?0.17. As c:iJe-~ulJ, J~hniQal $p~9tf]gi,tior:1s*limitin~r9o.r;i~fition klr
  • . Opefa!ion.3:*s.:1,"1;:rriergemcy ~6ra* Cbolih'9 Sy?Jerii _,;Qper~ting, l,\\9ti<?ri: E_ (9ri~ AQS _

'{~Ive. _ _..

i.hqpe!c{f?le), which te;iqt.i(re~.ari inoper~ble ~i09 v9:lve be*resJ6recl*~ithin 14 c;t_a,Y,~. ~as.not me.t.

Therefbre_; the.condifjdn de*si;:ribeq ii] this,L~fli&.reportc!-ble.under 10*CFF;l 50.73.(a)'(2)(i)fl3.), any

  • . opera,tion,9r c_~*ndition whii;:h ;~a~ prohibited by t_he pla'nt's T~ch.n.ica! £p~c~icaJi6ns.

E. -.. *correctiv.e.Acticins Th"e Division 1* SRV 1s21:.Fo41B~nd SRV ~s2{,F0S1B*winng.Was c~~rected and.a*post-,* -..

mainteha~c~ t~st conipietetl. *. Addit,ional ~:irrectiv~ ?Gtions will,be prdv_ic;ie,d 1n,a -revisiqn to this LEA.;.

I

.F.. *.*_*Previous Slmilar:q~currences.

The.re we;~ l')<?Pi.evious ~ve~~~.. !q!=)ntjfied involvirrn iDiswjfiqg of compori~nts similar tojhe ~9ndition ciesc~qee:l in tt'Jis licl?nsee.eveW,t report. -

1

.... G.

C.9ryiponer;it Failure :Pata:

Not.appiJc.~b[e.

u ~'

.... 1,,.

~.

~..

.._;,l,.-

l

,** \\ *-

~-

,,, ** '1 Page_3_ ~f *L> *

Retrieved from "https://kanterella.com/w/index.php?title=05000461/LER-2019-004,_Safety_Relief_Valve_Wiring_Issue_Results_in_Condition_Prohibited_by_Technical_Specifications&oldid=4704695"