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Brunswick Nuclear ProjectP. O. Box 10429

Southport, N.C. 28461-0429October 26, 1990 ;

FILE: B09-135100 10CFR50.73SERIAL: BSEP/90-0737

'U.S.-Nuclear Regulatory CommissionATTN: Document Control Desk

!it . Washington, Da C._20555

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BRUNSWICK STEAM ELECTRIC PIANT UNIT 1 |DOCKET NO. 50-325 i

LICENSE NO. DPR-71 '

LICENSEE EVENT REPORT 1-90-0 Q'

h. Gentlemen:

'

In accordance - with Title 10 of the Code of Federal- R ulations, *h-, enclosed:

Licensee Event Report is submitted. This report fulfil s the requirement for awrii. ten report within thirty (30) days of a re ble occurrence and is i

. submitted in accordance with the format set forth . .portaNUREG-1 1, September 1983. !

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L'h Very truly yours,

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F - J. L. Harness, General Manager '

Brunswick Nuclear Project

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.cc: Mr. S . D.- Ebneter -Mr.'N. B. Lo.

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Mr. C. W. Crawford- Mr. A. M.-Lucas Ms. T. A. Ward- Mr. A. B. Cutter Mr. L. H. Martin INPO

Mr. W. J . Dorman Mr. M. R. Oates Onsite LicensingMs. R. S. Gatewood Mr. H. A. Pollock SHEEC TrainingMr. W, P. Guarino Mr. J. J. Sheppard Ref. Libracry

. Mr. M.' D. Hill Mr. W. W., Simpson'

Mr. M. A. Jones Mr. R 3. Starkey, Jr.

Mr. B. P. Leonard Mr. G. E. Vaughn

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Brunswick Steam-Electric Plant Unit 1 o 16 t o 1010131215 1 |oF| 015*

' *" ' ' ' High-Pressure Reactor SCRAM While Performing PT-40.2.10 Duc To Erroneous

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>During a schedsled Unit ~1 shut down for a refuel / maintenance outage 1:oniSeptember 27, 1990,.. theireactor scrammed;on high pressure at- |< s

0348, .during; the performance of' periodic -test; (PT)'.40.2.10, Turbine .dK ^, ' Control /Stop Valves (TCV/TSV) Leak Tightness Testing. Prior to the I

f ' event, the . reactor was at approximately 22% power and the Emergency .j'

L, . Core ; Cooling Systems :(ECCS)' were operable in standby readiness.L Event ' . recovery: was' in ~ accordance with site. Emergency operating-

1 ; Procedures,- no e ECCSf or. Engineered Safety Feature ~actuations or |

L' tisolations other than. ' scram signals occurred. The event was |: occurred by erroneous procedural guidance, incorporated into the PT 1

J;from aivendor document, and defective. switches on the TSVs-whichallowed the TCVs to,open when the TSVs were closing.- This resultedp ,

s in' the turbine-' bypass valves (BPV) open' demand signal being limited 1'

L by1 the C Maximum , Combine Flow circuitry of the turbine control |.,

system.: TheX closure ' of the TBVs '' occurred reactor pressure to I

increase to the: SCRAM'setpoint. . Maximum power attained during.theSCRAM was 28%. This event had minimal safety significance as the .|

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W reactor'is analyzed for a high pressure SCRAM from ; full power. I'b .Past high pressure scram events were reviewed and found not to be

related-to this event. The procedure.will be rewritten and-theswitches will be repaired. 1

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Unit i reactor SCRAM due to high pressure during the p*Mormance of '!g

O turbine control /stop valves leak tightness testinr. '--

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INITIAL CONDITIONS

on September 27, 1990, the Unit i reactor was being shut down fora scheduled refuel / maintenance outage. The Emergency Core CoolingSystems (ECCS) were operable in standby readiness. The '"B" reactorfeed pump (RFP).was being held in standby by-placing its controllerin manual-and.' lowering.the pump speed until the discharge pressure-was'below1the forward feed point. -The "A".RFP was supplying the

|- vessel..in automatic under-the control of the master feedwater levelcontroller. At .0225',- the ~ generator was removed from the grid. TheUnit stabilized,at 9.45 psi, 24% power and 68% bypass. At 02 3 0, the 'turbine-was: reset and selected to-1800 rpm in preparation'for theV

-

performance a of L PT-40.2;10, Turbine Control /Stop Valves (TCV/TSV).LeakiTightness Test. At'0251,. power reduction by1rodiinsertion-'

continued while a.second reactor operatorf(RO) monitored the~PT. h,

.At 0334, theiTCV portion |of the PT was completed, unsatisfactory,.when'the turbine' failed.to. decrease speed to 600: rpm when the TCVs-were closed. ' At 0338, the turbine was returned .to ~1800 rpm to

y- _ perform the TSV' portion of the PT.,

L'. MENT' DESCRIPTION

- At 0346 a jumper was . installed, per the PT, in the turbine eleuro-hydraulic'controlE(EHC) cabinet to cause the: number (No,'):2-TSV to:close. 1The No.~1,:3, and 4 TSVs are slavedEto the No.12'and'also

.began.to'close. At;0347 the-BPV position increased to 60% and then<, .

returneduto 55%.'open, reactor pressure began- a gradual 1 increase topL

'

L 9 7 1 p s i'.' . At - 0 3 4 8 ,; BPV position ' decreased to 31% causing; anacceleration.of the pressure increase"to'approximately'5. psi perp" c

:second. . Withinf ten seconds reactor pressure reached the alarm |

; setpoint' of11025. psi'and three beconds later the pressure increased ,

L ; to the'. SCRAM fsetpoint -of 1035 psi and the: Reactor Protection System?

N (RPS) automatically inserted the. control = rods.. .During the. SCRAM. ,

t recovery, a; manual SCRAM signal was generated when the mode switch'

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4 Lwas placed to shut down, in ecordance with the site Emergency:'Operating Procedures-(EOPs), and n second RPS signal was generated

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p' 'on? SCRAM 7 discharge volume (SDV) Hi-Hi. level. After the SCRAM,reactor pressure -decreased belo'.< the discharge pressure of "B" RFP!"

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which remainedi at its manually set speed. At 0351, the "B" RFPoverfed the vessel and a.high reactor level tripped the "A" and"B" RFP turbines', the main turbine and the high pressure ECCSturbines. At 0357, the RO reset the."A" RFP turbine and placed the ..Startup Level. Control Valve (SULCV) in service. During the event

Lthe highest pressure was 1042 psi, the lowest level was 167 inchesand : the maximum attained power was 28%. No ECCS or EngineeredSafety Feature (ESP) actuations or isolations, other than the SCRAMsignals, occurred during the event.

EVENT INVESTIGATION'

PT''.0.'2 10Lwas a site procedure which has been performed once oneach Brunswick unit. The procedure was based on guidance providedin z vendor . document GEK-25406A: and.had an - 18' month performancefrequency. 'The-test is'not a Technica3 Specification required"

surveillance.

on-September 27,.1990, the test was performed on-Unit 1.. During'

g' ':the TSV portion of the test,Lthe TSVs were initially full opon andthe TCVs were " cracked" open to' supply enough steam to keep the

Lturbine at 1800 RPM.' The turbine' bypass ~ valves-(BPVs) wereibeingutilized to control reactor-pressure to.the condenser. When the'

; jumper was installed allowing the'TSV to-close the TCVs. began tot

open,nas expected by PT-40.2.10 and GEK-25406A. However, a reviewt /E of:EHCisystemSlogic?printsiindicates thattthe TCVs should remain

' closed any time the TSVslare closed except during the shell warmingimode f of . operation. Therefore,-if the" equipment: Efunctions :per

-- design, the PT and'GEK are incorrect.'

'During this-performance of PT-40.2.10 'tho'TSV lihit switches:didnot operate properly.and as the TSVs closed the TCVs opened.in.anattempt . to " maintain thel selected speed' of - 1800 rpm. If the-

: equipment,had, operated properly.an. interlock between the TCVs.andthe:TSVs should have; automatically lowered the " Load Limit" to zero,

Landiprevented TCVs fromLopening. .The11nterlock was tested after;the.'eventi and three ' ' of ' the four switches were' found . to .bemalfunctioning. ' The -combination LofL the: jumper installed by theprocedure and the~ defect in the TSV interlock circuit-allowed.thecontr W valve amplifier. ' (CVA) to generate an increasing demandsignr. to open,the TCVs.

JAnother ' turbine control circuit called " Maximum Combined Flow"(MCF)1 monitors the summation of the TCV and BPV demand. ThetMCF

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setpoint-is 110% of rated flow. If the summation exceeds 110%, the~BPV position demand will be limited. In this instance the TCVsopened.in an attempt to maintain turbine speed at'1800 RPM because

|3 . of the.TSV switch failure to decrease the Load Limit to zero.- As -the TSVs,' closed the BPVs should have opened further to maintainreactor pressure. Initially the BPVs did open further, however, asthe MCF limit was reached, the BPVs began closing in response tothe MCF ' control circuitry resulting in the observed reactorpressure-increase and resulting SCRAM.

A--review of'the Unit 2 performance of the PT on-September 9, 1989,,

Lrevealed that1 the MCF setting was at 130% combined BPV and TCVt

. demand instead of the 110% setpoint. The 130% setting' allowed theTCVs to open'without limiting the'BPVs.~. ~ The setting was restoredto'the 110%-setpoint during the Unit 2 refueling outage.

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^Pastireactor-high pressure events were not related.to this' event. '-

ROOT CAUSE I

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Theiroot.cause of'the. event was erroneous procedural guidance and-. defective. switches on the'TSV. ;

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been; removed from use. -The procedure will ; be' i

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. revised such that.the test may be satisfactorily performed.'

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The U-1 TSV-limit switches;will, be ' repaired. _ An investigation into'

4 the"cause of theiTSV switch failures:-will~be co.iducted. The U-2:,

" ' 1TSV limitrswitches will"be checkedifor: proper operation.u i ,.

GE L has been~' requested ito inform the' industry of the' GEKL ,

| inadequacies.. 'CP&L. will; initiate _an' appropriate' industry~

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SAFETY SIGNIFICANCE

The safety _. significance of this event is minimal. The reactor is. analyzed for,a pressure transient from full power. This event was -within the bounds of that analysis. No ECCS or ESF actions orinitiations--other than the SCRAM signals occurred.

-EIIS CODES-

System /ComDonent- Code

TCV TRB/CV

--TSV TRB/SHV

BPV TRB/*

'RFP SK

EliC . TG

RPS. JE

SDV AA/*!;-

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SULCV SD/LCV

CVA: TRB/CV/ AMP'

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