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

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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)
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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

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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)

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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..

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

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

Clinton Power Station, Uriit 1 *

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05000461

. YEAR

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2Q1.9 004

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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.;.

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.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. -

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