ML17266A225

Summary of 800620 Meeting W/Util & C-E in Bethesda,Md Re 800611 Reactor Trip & Cooldown on Natural Circulation

ML17266A225
Person / Time
Site:	Saint Lucie
Issue date:	06/25/1980
From:	Nelson C Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TASK-1.C.1, TASK-TM GL-81-21, TAC-47150, TAC-47151, TAC-47170, TAC-47179, TAC-51994, NUDOCS 8007100161
Download: ML17266A225 (24)

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O UNITED STATES NUCLEAR REGULATORY COMMISSION WaSHWOVOe. D. C. 20bba June 25, 1980 Docket No. 50-335 LICENSEE: Florida Power 8 Light Company (FPulL)

FACILITY: St. Lucie Unit No.

1

SUMMARY

OF MEETING,WITH FP8rL AND COMBUSTION ENGINEERING (CE)

REGARDING ST.

LUCIE UNIT NO.

1 COOLDOWN ON NATURAL CIRCULATION'n June 20, 1980 a meeting was held in Bethesda, MD regarding the June ll, reactor trip and cooldown on natural circulation at St. Lucie Unit No. 1.

Significant points discussed are summarized below.

Enclosure 1 is a list of attendees.

Discussion A brief chronology of the event was presented with traces of parameters enclosed as Enclosure 2.

The plant experienced a complete loss of component cooling water (CCW) to the reactor coolant pumps (RCP).

This loss was due to a direct short on the terminal board for a solenoid operated CCW comon return valve from the RCP's.

Plant procedures allow ten minutes to correct the problem before securing the RCP's.

Subsequently, the reactor was tripped and the RCP's secured.

About three minutes after shutdown one RCP was run briefly to aid natural circulation flow.

The licensee stated that intermittent RCP leakoff flow alarms were actuated and that subcooled margin remained within the range 65 to 180'F subcooled during the cooldown.

The 11censee indicated that a steam bubble had formed in the head of the reactor vessel during cooldown.

This was indicated by abnormal pressurizer level changes during charging operations and was apparently due to elevated temperatures in the hydraulically stagnant area of the upper head.

The possibility of steam bubble formation was confirmed with an analysis by CE using an in-house model.

This model decoupled the vessel head region from the rest of the reactor vessel with respect to temperature.

As a result of the analysis CE issued an information bulletin (Enclosure

2) warning of the long vessel head cooldown times which may be required (10-15 hours) and recommending actions to maintain plant conditions until the vessel head has cooled should a

bubble form.

The licensee indicated that while in the shutdown cooling mode of operation some primary'oolant may have leaked to the refueling water tank through LPSI 1B pump's recirculation line.

The isolation valve in this line was found not to be completely shut.

The licensee stated that there were no indications of radio-activity release.

While on shutdown cooling LPSI Pump 18 was operating in the injection mode with its recirc line open.

St. Lucie Unit No.

1 For corrective actions the licensee has modified its procedures to include the CE guidelines and installed backup means (additional air supplies and manual rachet ) of opening the CCM containment isolation valves.

Conclusions The NRC staff indicated the need for more detailed analyses of the natural circulation cooldown including consideration of secondary makeup supplies.

In addition, the impact of steam bubble formation and its effects on depres-surization rates may have to be considered in the analysis of other transients.

This information will be requested of the licensee by separate letter and does not have to be resolved prior to restart.

The NRC's Office of Inspection and Enforcement will further review the licensee's corrective actions as well as the acceptability of operating one train of the shutdown cooling system in the injection mode with the other train operating in the shutdown cooling mode prior to plant restart.

Enclosures:

1

~ List of Attendees

2. Chronology of Events, Evaluation, Actions Taken 8

Summary cc w/enclosures:

See last page Chris C. Nelson, Project Manager Operating Reactors Branch P3 Oivision of Licensing

Enclosure 1,

JUNE 20, 1980 MEETING WITH FP&L - ST.

LUCIE UNIT NO.

1 - ATTENDEES NRC Chris C. Nelson Themis Speis Brian Sheron Ed Jordan Edward Blackwood Jerry Mazetis Kris=Parczewski Phil Matthews George Lanik E.

V. Imbro

'. A. Clark J.

S. Cresswell Monte Conner Chang Li Thomas R. Wolf H. F. Conrad CE Charlie Brinkman R.

S. Turk R.

S.

Daleas J.

C.

Mouhton R.

E. Wolf FP&L C.

M. Wethy J.

A. DeMastry H.

N. Paduano

~

~

r Enc1osure 2

CHRONOLOGY OF EVENTS I I, EVALUATION D

SAGER A.

FPaL CE I II, ACTIONS TAKEIT IY, SUlWRY D.

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'IGURE Ai-18 JUNE 12.

1980 NRTURRL CIRCULATICN COOLDONN LOOP 8

RCS. HIQE RRNOF TEMPERATURES 900 saa C5 700 6ao SGO 400 3aa 200 100 12,00 I

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1980 NFITURRI CIRCULATION CQQLOQNN PZR LEVEL.

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FIGURE Ri-3 JUNE i2. i980 NATURAL CIRCULRTICN CCOLDQHN PZR HIDE RANGE PRESSURE 3600 3200 CC 2800 2400 z

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80-0034 hN AQVISOltY COSCKltlCINO A TECHNICAL DKVKLOFNER7 RELATED 70 THE AftLICA7JON OS OPERATION OF NIJCLEAS t LANT EOVWCElaT SUltLlED 5Y CDNSUSTlON ENGlNEESIÃG.

June 20, 3980 NltTORAL CIRCULATISl COOLOOM IHTROOUCTIDN:

On June 32, 3%0, C-E ms fnfomel by FP3L that unexpected varfatfons I I'I a natural cfrculatfon cooldalm at St. Lucfe T.

The varfat$ ons Idcrc detarm}ncd to have resulted frea the expansion and collepse of a stcam vofd fn the Reactor Vessel (RV1 head region.

This bulletfn prov)des details currently knoll ibout thts event and ap-praprfate operational guidance for ut0 Tftfes with operating C-K?lSSSs OISCtlSSESt:

FoTTollfng a Toss of Component CooTfng Mater. to the RCPs. St. I.ucfe L

~sxxnnmcn

. an nxtsndf titus natural csrcu1 at sancaaldaun ta cata shutdaun candftsann.

RCS depressurfzatfan vfa pressurizer auxfT fary spray ~as inftfa ed approxfrateiy 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the reactor trip.

Qurfng depressurfzatfon, saturation condftfons mre reach d fn the RV head region which Tfafted further depressurfzatfon untfT the head region had cooled off.

Under natural cfrculatfon flew conditions there was afnfaeT coolant fTm fn the upper head region and effectfveTy aIT cooTing ms by heat Toss to the aWfent ar by reactor coolant surge flm through the head regfon.

An RCS'pressure appropriate for fnftiatfng shutdown coalfng (SCS) ms attafned approxfmtely 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> foTIollfng the reactor tr fp.

Gurfng this event, the core regfan ms al~ys sfgnfffcantTy subcooled.

In the event of a natural cfrculation cooldsasn ft should be realfzed that cooifng of tha vessel head regfon cay be Tfmftfng fn establfshfng SCS entry condftfons.

Cooling of the RV head region ray requfre. as such as TO to 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />.

Perfodfc attempts tc depressorfze to SCS entry conditions can be alade AfTe llatchfng for indfcatfons of void formation.

Mhen SCS entry condftfons are achfeved, thc shutdecn cool fng system may he al fgncd fn accordance. with operating pro-etures.

lhrfng depressurfzatfon.

fomatfon of a staw.vofd fn the RV head auld be fndfcated by a rapfd fncrease fn pressurizer level llhfle deliverfng auxiliary spray,~

bc f4aa4g<

decrlase fn pressurizer level lichen charging fs rcalfcmed to the RCS loop e re-spollses are. indicative of an expanding void fn the R'l head as the pressurizer fs sprayed. and collapse of the steam void in the RV head as charging fs dfrected: to the loop.

These fndfcatfons uay be preceted by an fndfcation of Tetdoscn floe fn excess of charging flue ff the pressurizer Teve? amtrol systea has beer fn autacatfc durfng the coo'adown.

Upon fndfcatfon of a steacl void the following actfons are recoeocndef in order to eafntafa pIant condftfons untfl the RV head has cooled:

Isolate I'etdolln.

2.

Stop further.

RCS cooTden untfT fndfcatfans ot'V head steau vafd cease.

3.

Energize pressurfzel heaters to Iflxft rate of depressurfzatfce.

4.

Operate charging and auxfTfary spray to nafntafn pressurfzer Tevel bebaen 30" and Z(5 fn order to Tflnft vofd expansion.

STRTUS:

The event fs currently betng'rcvfclled.

Actdftfonal operator gufdance,&TT Tle incorporated into. C-E tratntnq programs and fonearded to utflftZ operatfnq staffs as appropriate.

THC HdFONitATIONCOICTAlIISO IN TllIS'RlellleC&%IddOIKlxOSULLETINlxNOVK%0elF OC QNOCN TlIOTRNSSIOF TYIS ICVCLSA7lST%~~1 SYXTI%4 CXHCTNACT SON T~ AFFLICASLXFLAUNT A4 A SKNlOCK TO YOIINONOAN IZATIOH. AS A $NSVLT AHO SIROCCO Ot%NATKeS OF YOLtN FLAlCT IS ~LtVKLY%5%19% YOLIN 07IITNOLAl00 NSSFOASISILITY, AIIO INVOLVSS IASEY FACADE% OLID WITHIII~ KNONLSOOt TTI% INFONQATION SIAY SS VTII IS%0 OICLY WITH THE MldOSNSTAIdOIIIO THAT OS IIAXCS lOO NANNAPtZlSI ON NKFIlKXfJA'ATIONS, CIIPIIKSSSO OII ~ICCl, INCLIIOIIIOTHC WAQlIJJCTSSSOF FITNCSS ISON AlxAITtlC~FtiNFOSIIONISISNCHAIdT ASILITY.WIT%%II~TO TH% ACCWIACY OII LKKF~CSC Oln TtlC INFO~TIOHCONTAIICCO Ial THIS SULLCTIII.APCO TIdAT~ OISCLAI485, AI4O YOV ARSON'LLLIASILITY,IIOIaSOLICHi0aCS OIIOTHCNWISS, ASA NCS4lLTOF YOMI% QSCOF'THIS IHtOfM4ATA&4.

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IN.COR E INSTRUMENTATION SUPPORT PLATE IN-CORE INSTRUMENT GUIDE TUBE CEDM NOZZLE INSTRUMENTATION NOZZLE CONTROL ELEMENT ASSEMB LY FULLY WITHDRAWN ALIGNMFNTPIN UPPER GUIDE STRUCTURE 42" I D OUTLET NOZZLE SUR VE I LLANCE HOLDER IL 30" I D INLET NOZZLE CORE SUPPORT BARREL 137" ACTIVE CORE LENGTH CORE SHROUD FUEL ASSEMBLY SNUBBER CORE STOP

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Maine Yankee Atomic ower Company CC:

E.

W. Thurlow, President Maine Yankee Atomic Power Company Edison Drive

Augusta, Maine 04336 Mr. Donald E. Yandenburgh Vice President - Engineering Yankee Atomic Electric Company 20 Turnpike Road

Westboro, Massachusetts 01581 John A. Ri tsher, Esquire Ropes

& Gray 225 Franklin Street

Boston, Massachusetts 02110 Mr. John M. R. Paterson Assistant Attorney General State of Maine

Augusta, Maine 04330 Mr. Nicholas Barth Executive Director Sheepscot Valley Conservation Association, Inc.

P. 0.

Box 125 Alan, Maine 04535 Wi seas sett Pub 1 ic Library Associ ati on High Street Wiscasset, Maine 04578 Mr. Rob.rt R. Radcliffe Office of Energy Resources 55 Capitol Street

Augusta, Maine 04330 Robert M. Lazo, Esq.,

Chairman Atomic Safety and Licensing Board U.

S. Nuclear Regulatory Conmission Washington, D.

C.

20555 Dr. Cadet H.

Hand, Jr., Director Bodega Marine Laboratory University of California Bodega Bay, California 94923 Hr. Gustave A. Linenberaer Atomic Safety and Licensing Board U.

S. Nuclear Reaulatory Commission Washington, D.

C.

20555 Mrs. L. Patricia Doyle, President SAFE POWER FOR MAINE Post Office Box 774

Camden, Maine 04843 First Selectman of Wiscasset Municipal Building U. S.

Route 1

Wiscasset, Maine 04578 Director, Technical Assessment Division Office of Radiation Programs (AW-459)

U.

S.

Environmental Protection Agency Crystal Mall 82 Arlington, Virginia 20460 U.

S.

Environmental Protection Agency Region I Office ATTN:

EIS COORDINATOR JFK Federal Buil ding Boston, Massachusetts 02203 Stanley R. Tupper, Esq.

Tupper and Bradley 102 Townsend Avenue Boothbay Harbor, Maine 04538 David Santee Miller, Esq.

213 Morgan Street, N.

W.

Washington, D.

C.

20001 Mr. Paul Swetland Resident Inspector /Maine Yankee c/o U.S.

NRC P. 0.

Box E

Wiscasset, Maine 04578 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.

4853 Cordell Ave., Suite A-1

Bethesda, Maryland 20014 State Plannina Officer Executive Department State of Maine 189 State Street

Augusta, Haine 04330

MEETING

SUMMARY

DISTRIBUTION Licensee:

Dr. Robert E. Uhrig

• Copies also sent to those people on service (cc) list for subject plant(s).

6 Docket File NRC PDR L

PDR TERA NSIC ORB Rdq

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NRR Rdg HDenton ECase DEisenhut RPurple RTedesco TNovak.

GLainas RReid TIppol ito SVarga DCrutchfield RAClark ORB Project Manager -CNel-son Licensing Assistant -PKreutzer OELD AEOD - JHeltemes IE-3 SShowe (PWR) or CThayer (BWR), IE

RFraley, ACRS (16)

Program Support Branch GZech JOlshinski NRC Participants TSpeis BSheron EJordan EBlackwood JMazetis KParczewski PMatthews GLanik EImbro JCresswell MConner CLi TWolf HConrad

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