05000461/LER-2019-003, Reactor Water Cleanup System Differential Flow Instrumentation Inoperable

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Reactor Water Cleanup System Differential Flow Instrumentation Inoperable
ML19333B814
Person / Time
Site: Clinton Constellation icon.png
Issue date: 11/14/2019
From: Chalmers T
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
U-604516 LER 2019-003-00
Download: ML19333B814 (4)
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LER-2019-003, Reactor Water Cleanup System Differential Flow Instrumentation Inoperable
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(ix)(A)
10 CFR 50.73(a)(2)(1)
10 CFR 50.73(a)(2)(v), Loss of Safety Function
4612019003R00 - NRC Website
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text

Clinton Power Station 8401 Power Road Ch,:itoo, IL 61727 U-604516 November 14, 20*19 u.s. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C. 20555-0001.

Clinton Power Station, Unit 1 Facility. Operating License No. N_PF-62 NRC Docket No. 50-461 Su~ject: Licensee E'-'.ent Heport 2019-003-00 10 CFR 50.73 SRRS. 5A.108 Enclosed is Licensee Event Report {LER) 2019-003:-0ff: Reactor Water Cleanup System.

Differential Flow.Instrumentation Inoperable. This report is being submitted in accordance with the requirements of 10.CFR 50.73.

There are no regulatory commitments contained in this -report.

Should you have any_questions.conceming this report, please.contact Mr. Dale Shelton, Regulatory Assurance Manager, at (217) 937-2800.

  • RE?spectfully,

Attachment:

Licensee Event Report 2019-003-00 cc:

Regional Administrator - R'egion Iii*

N*Rc Senior Resident Inspector - Clinton Po~er Station Office of Nuclear Facility.Safety - Illinois-Emergency Management Agency

NRC FORM368 (04-2018)

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OUB: NO. 3150-0104 EXPIRES: 03/31f.Z020

. l:ICENSEE EVENT REPORT (LER).

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1. Facility Name 3.Page Clinton Power Station, Unit 1
  • 2. DockeJ Number 05000461

'1 OF 3

4. Title
5. Event Date
6. LEA Number
7. Report~
  • a. *Other Facllltles _Involved Sequential Rev

,. Facility, Name DocketN-Month Year y.,.,

llonth Day Year Day NLmbw No 05000 Facility Name Docbl Number 09 16 2019 2019 003 00 11 14 2019 05000'

9. Operating Mode
11. This Report Is Submitted Pursuant to the Requirements of 1 O CFR §: (Check all that apply)

D 20 2201(b)

D 20.2203(a)(3)(1)

D 50.73(a)(2)(u)(A)

D ~.73{a)(2)(V)l1)(~)

3 D 20 2201 (d)

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

D 50 73(a)(2)(l~(B)

D 50 73(a)(2)(vlll)(B)

D 20.2203(a)(1)

D 20 2203(a)(4):

D 60.73(a)(2)(lu)

D 50.73(a)(2)(ix)(A)

D 20 ~(a)(2)ITT

,0 50 36(c)(1)(l)(A)

D 50 73(a)(2)(1V)(A)

  • D 50 73(a)(2)(x)
10. Power Level
  • D. 202203(a)(2)(n) tJ 50 38(c)(1)(u)(A)
  • D 50.73{a)(2)(v)(A)

D 73.11(a)(4)

D 50 36(cJ(?r*

D 50.7-3(a)(2)(v)(B)

D i3 11 (a)(si o 20 220s(a)(2)(1V)

[] 50 48(a)(3)(u)

D 60 73(a)(2)(v)(C)

D 73 n(a)(1J 000

  • o 20.~a)(2)(v)

D 50.73(a)(2)(1)(A)

D 73 nca)(2)(,J D 20.220~(a)(2)(vl)

D 50 73{a)(2)(1)(B)

D 50,;3{a)(2)(v11)

D 73.77(a)(2)(11J

,----:------~-*--

L:____: --* __ I :o 50 73(a)(2)(1)(C)

.. D Other (Specify in Abstract below or In NRC Fann 366A)

12. Licensee Contact for this LER.

Wcensee Contact Mr. Dale Shelton,* Regulatory Assurance Manager Telephone Number (lnch-!de Area Ccxle)

(217) 937-2800 Cel.18e.

Syatem Component Component Manufacturer Reportable to ICES

14. Supplemental Report Expected

~nth Day Veer D Yes (If yes, complete 15. Expected Subm~on Date) [81 No*

15. Expected Submission Date Abstract (Llmlt to 1400 spaces, I e., approximately f4 smgle-spaced typewrttten lines)
    • on 09/16/19,*at 0817 CDT, at approximately 0% power during shutdown for refueling outage C1R19, th*a Division 1 and Division 2:Raactor Water Cleanup* (RT) system differential flow instrumentation was declared inoperable due to failing*

downscafa caused by flashing in *the sensing lines that occurred durin'g reactor cooldown. The Division 1 and 2 *RT' differential flow instrumentation ware declared,inoperable iri accordance with Techrnc:a.1 Specification (TS) 3.3.6.1. The cause of this event was unit shutdown procedures were not' optimized to increase subcooling in the RT system during reactor c0oldown. The system aiignment was changed in accordance with procedures to increase subcooling and indication was restored by 0852 CDT -on 09/16/19. Procedures governing unit shutdown will be revised to increase subcooling in the RT system during reactor cooldown to reduce the likelihood of flashing*in the sensing lines.. This condition mat the reportability requirements* of 10 CFR 50.73(a)(2)(v)(D), any ev*ant or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

NRC FORM 366 (04-2018) (04,2018)

U.S. NUCLEAR REGULATORY COMMISSION Af'PROVED BY 0MB: NO. 3150-0104 EXP_IRES: 03131fl020

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(¥i LICENSEE EV~NT REPORT (LEA)

CONTINUATION SHEET (Sae NUREG-1022, R 3 for 1nstrucbon and guidance for comple1mg thlS form t)ttp;//www nrc.goy/read1nq-rrn/doc-co~leptions!nuregs/staff/sr1022/r3/l 6strna!ed-burdefl per response to cmw'l'lllh ~

mandatory cdleclloo reqllesl 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessoos ~

are 1rcoiporatoo ll1lo the l!censmg proc86S and led back to OOJStry Send corrmenls regarding burden astrrnate lo the lrroimabon SeMces Brandl (T-2 F43), U S Nuclear RegJalory Cormisslon, Waahmgtoo, oc 20555-0001, or by* 8-fllfl!' to lnfocciecls Resoorce Q r,c,p, and to lhe, Desk Ollcer, Ofhce of lrvormalloo end Reg\\jalory Ailllrs, ~08-1020'2, (3150{)104), Oflce of Maragernefll and Budget, W~. DC 20503 tt a moorm llSed to ITTlJXlS8 !Ill irrormalioo calection ~

not ci5?ay a Cl.mffy v*l 0~ ro-ird runber, the NAG l1lllY not cordJct or (lfloosor, and a parson IS not required to respood to, the lrrormallon c:ollection.

1. FACILITY NAME.
2. DOCK;ET ~UMBER Clinton Power Station, Unit 1 05000461
3. LER NUMBER SEQUENTIAL NUMBER REV NO.

YEAR 2019

  • 003 00

~RRATIVE Pu\\NT AND SYSTEM.IDENTIFICATION General Electric -- 1;3oiling Water Reactor, :,3473 Megawatts Thermal Rated: Core Power Energy Industry Identification System (EIIS) codes are ident)fied in text as [XX].. -

EVENT IDENTIFICATION

~

Reactor Water. Cleanup System Differential Flow Instrumentation I !:)Operable A.

Plant Operating Conditions Before the Event

Unit: 1 Mode: 3' Event Date: September 16, 201 g Mode Name: Hot Shutdown B.

Description of Eyer,~

Event Time: 0817

. Reactor Power: 000 On *september-1.6, 2019, at 0817 CDT, at approximately 0% power during shutdown for r~fueling outage C1H19('the Division 1 and Division 2 Re~ctor Water Cleanup (RT) [CE] system dtffer~ntial flow instrumentation [Fl] were declared inoperable due to failing downscale caused by flashing in the sensin*g lines that occurred during reactor cooldown. The.Division 1 ~nd Di.vision 2 RT differential flow.

instrumentation were declared inoperable in accorda:nce with Technical Specification (TS) 3,3.6.1, Conditions D and E, Which require restoring at least one division of instruments to Operable status

  • within bhe hour. In respppse to this condition, the system aligfunent was changed !!i accordance with.

procedures to increase* subcooling and restore indication: Division 1 and 2 RT differential flow -

- - instrumen~ation were declared Operable at 0852 CDT on September 16, 2019.

- C.

Cause of the Event

Th!:3 P.lal)t was being shuf d9wn in accordance with the Unit. Shutdown procedure '(CPS 3006.01) when the DMsioh 1-.and Division 2 RT-system differential flow instrumentation failed downscale.. After the RT system differential flow instrumentation was declared inopera~le, an Operator identifi~d that the RT system operating p_rocedure *(CPS 3303.01) provides instructions to minimize flashing as reactor pressure is lowered during reactor cooldown. This proceoure was used to restore the RT. :..

system to Operable status. Because the Unit Shutdown procedure does not direct the Operator to refer to glifdance provided in the RT system operating procedure (CPS 3303.01) to minimize flashing as reactor pressure_ is lm~ered during pla~t.cooldown, the cause of this even~ w~s determined to be. Page...i.._ of~

A' (CJ.4-2018)

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3160-0104 EXP_IRES: 03/31/2020

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LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET-

- (See NUREG-1022, Fl3 for tnstructlon and guidance* for completing ttus form htto*/twww.~rc.gov/readlna-rm!dop:eollectJoos/nuf895{staff/sr192f0'}

Estrnaled burden per response to ccxilply 11111h ~

miniato,y cd~ recµist 80 hous. Reported less(xis learned are mcorpollllad rrto the licensrJg process lr1d led back to inciJstJy Send corrments ragaidiig burden estmaJe to the lnlo!rnaboo Serv!ces Brard1 (T-2 F43), U S. Nuclear ~

Camnssioo, WBBIJngtoo, DC 20555-rol1, or,by. 8-!Tllli lo lrroccllecls ResrurceO ~. and to fie D8;8k Olllcer, Ofllce of ~on 1¥\\d A~ Alfrus, NEOB-10202, (3150-0104), Office al Mai1arJoom ero Budget. W~, DC 20503 U a meMS used lo rnpa;e an rlfoonallon caJeclron doo5 not display a CUIT8lily Vllild OtJB cootrd nlirber, the ~

may not cmwct or 8J)OOSOI', and a person Is not required lo respond to, the lnlonnatlon rolectron

3. LEA NUMBER Clinto*n Power Station, Unit.1 YEAR 05000461 2019 -

SEQUENTIAL NUMBER 003 NARRATNE 1,1nit shutdown procedures were not optimized to increase subcooling in the RT system during cocildown,_ which resulted in flash)ng in the sensing lines.

D.

Safety Con~equences REV NO.

00.

The condition described in this LER rendered the Leakage Detection System incapable of performing

. its isolation function, which met the reportability 'requirements _of 10* CFR 50.73(a)(2)(v)(D), any event or condition that could have prevented the fulfillment of the safety function of structures or systems *

  • that are needed to mitigate the consequences of an accident. There were. no safety consequences associated with the event described in this report as the unit was in Mode. 3 at the time of th~ event and the condition existed for *1ess than thirty minutes, which is within ttie TS 3.3.6.1 Required Action time to*restore at least one division of instnJments to Operable status within one hour. In additi9n, manual isolation capability and automatic isolation capability in respons~.to low reactorwater Jevel remained availabl'e.

E.

(1)

(2).

Corrective Actions

.The system alignment was changed.in accordance with procedures to incre<<::1se subcooling *

Procedures *governing unit shutdown* will be revised tp better utilize existing*guidance to increase subcooling i~ the RT system during reactor coold~wn, ~hich will reduce the likelihood of flashing ilJ th.a sensing. li~es.

F.

Previous Similar Occurren~*s LEA 2015-001-00 reported a loss of Division *1 and 2 RT differ~ntial flow instru,:neritation due to leak-by resulting in voids in the RT system that caused differential flow instrumentation to provide false readings.. The actions taken for LER 2015-001-00 would not have prevented the condition described in this LER.

  • G.

Component Failure Data

Not applicable.

I

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