ML20012A030

Summary of Operating Experience 1989

ML20012A030
Person / Time
Site:	Grand Gulf
Issue date:	02/27/1990
From:	Cottle W SYSTEM ENERGY RESOURCES, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AECM-90-0042, AECM-90-42, NUDOCS 9003080160
Download: ML20012A030 (10)

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G b February 27, 1990 U.S'. Nuclear Regulatory Commission Mail Station.P1-137 '

N Washington, D.C. '20555 +

i Attention: Document Control Desk I

, Gentlemen:

SUBJECT:

Grand Gulf Nuclear Station #

t Unit 1-Docket No. 50 416' -

• A License No. NPF-29 1989 Annual Operating Report AECM-90/0042 Plant Staff iu. transmitting the Grand Gulf Nuclear Station (GGNS) Unit l'

' Annual Operating Report for 1989. This report is sent in compliance with the requirements of Grand Gulf Technical Specifications 6.9.1.4 and 6.9.1.5

.s and in accordance with the reporting program described in Regulatory Guide 1~.16', Revision 4, Part C.1.b as niodified by the NRC letter to SERI dated May 25, .t987 (MAEC - 87/0131). -1 Provided as attachments are:

1. A narrative summary of operating experience during the year 1989.

2. Main Steam Line Safety Relief Valve challenges

3. A tabulated annual report of personnel exposure greater than 100 mrem /yr.

4. .A summary of failed fuel indications / inspections.

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/e 4 Summary of Operating Experience 1989 l

. The following is a summary of Grand Gulf Nuclear Station (GGNS) Unit 1 .

operating experience for the 1989 calendar year. During 1989,-the reactor was critical for 7,005.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> with the generator on line for 6,818.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

The plant was on line 157 days prior to the Third Refueling Outage (RF03)-

which began on March 18, 1989. The outage was completed on April 30, 1989 y

.for a duration of 43 days, 'The plant resumed normal operation when the-generator ~was synchronized at 1032 on April 30,-1989.

t An Alternate Decay Heat Removal System (ADHRS) was a contributing factor'to the short outage duration. The ADHRS was designed to be placed in servfce the day following reactor shutdown which allowed early performance of maintenance activities on the shutdown cooling common suction line;-  ;

therefore, decreasing outage duration by approximately two weeks. No system other than ADHRS has a high enough heat removal rate to be considered an alternate decay heat removal system, until at least day 34 of an outage.

Normal' operation continued until May 1, 1989 when an erratic response of ,

Flow Control Valve (FCV) 'A'.was observed. Reactor power was decreased and_ -

held at'approximately 31% with reactor recirculation pumps running at-slow ,

speed for initial investigation. On May 4, 1989 reactor power was decreased'.

to approximately 5% for a drywell entry inspection of FCV.'A'. Binding in the position feedback sensor was discovered and repaired. Another problem surfaced when the reactor was placed in Operational concition 2, Startup on

'May 5, 1989.'

During power ascension at approximately 4% power, feedwater , isolation valve

~F065A failed to open on normal motor torque. _After unsuccessful attempts !;o manually-open the valve, the reactor was placed in cold shutdown to inspect and repair valve F065A. During _ the' shutdown process, the reactor scrauned on low-water level due to feedwater level control problems (LER 89-006). l The F065A valve stem was replaced-and generator synchronization occurred on May 8, 1989. Total outage duration was'104.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

'On May 13, 1989,.the reactor was placed in cold shutdown to investigate high vibrations on reactor recirculation pump 'B'. Investigations disclosed a 300 circumferential crack on it's shaf t. Rotating assemblies for reactor recirculation pumps 'A' and 'B' were replaced. Generator synchronization occurred on June 2, 1989. Total outage duration was 450.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. System L Energy is continuing to work with General Electric and the BWR Owners Group

-in analysis and resolution of this matter.

On July 22, 1989, the reactor automatically scrammed due to a lightning induced erroneous indication of high reacter power by the Average Power Range Monitoring (APRM) System (LER 89-010). Generator synchronization

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occurred on July 23, 1989. Total outage duration was 28.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

ANOPERPT/SCMPFLR - 2 *

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i F On July 29, 1989, reactor power was decreased to approximately 804 to  !

replace the Reactor Feedpump Turbine 'B' controller. power ascension  !

resumed after performing control rod surveillances and pattern adjustments.

Normal plant operation resumed until August 14, 1989 when low condenser [

vacuum caused a main turbine trip and subsequent reactor scram (LER 89-012).  ;

The low condenser vacuum resulted from a failed turbine-to-condenser i expansion bolt. The plant was placed in cold shutdown and the expansion belts for all three condenser sections were replaced._ i 3

Other problems and corrective actions associated with the reactor scram were I as follows: l o Failure of one control rod to fully insertt Extensive testing and analysis of the Control Rod Drive (CRD), by

• General Electric and System Engineering, failed to disclose a.

i. cause for the CRD failure. It is suspected that multiple _ failures ,

within the CRD Hydraulic Control Unit (HCU) caused the control rod not to fully insert. All major components of the HCU were  !

replaced or rebuilt and the CRD was successfully tested numerous  !

times both prior to startup and with the reactor at p'rkr.

o Scram discharge volume failed to drain:

The'cause was attributed to a closed air supply throttle valve.

The valve which is located near other equipment was inadvertently i bumped close as workers climbed to reach the equipment. The air  !

throttle valve was repositioned and locked to prevent recurrence.

f o one inboard Main Steam Isolation Valve (MSIV) failed to close  ;

(LER 89-013) j Investigation revealed a faulty control solenoid valve in which -

indentations were shown in the seat material of the disc holder '

subassembly. A missing piece from the seat material became lodged t in the solenoid exhaust port which caused the MSIV not to close.

All inboard and outboard MSIV solenoid valves were either replaced or rebuilt. prior to start-up to prevent other potential failures.

An accelerated replacement / refurbishment schedule was initiated .i and a potential design change will be considered for implementation during the Fourth Refueling Outage (RF04). This condition was also reported pursuant to 10CRF21.

Generator synchronization occurred on August 23, 1989. The outage duration was 225.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, l

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12 On November 7, 1989, a second lightning induced automatic scram occurred due to voltage spikes to the Average Power Range Monitoring-(APRM) System (LER 89-036). System Energy initiated a project for installation of lightning

' dissipation arrays on all vulnerable structures to prevent possible-p lightning induced voltage spikes. The project is near completion except for i arrays which cannot be installed during plant operation, such as switchyard equipment.- These arrays will be installed during the fourth refueling outage.' Generator synchronization occurred on November 9,'1989. Total outage duration was 34.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

On November 30, 1989, reactor level oscillations with a magnitude of 4 to 5 inches were observed. Chart recorders were connected to feedwater. systems

[ to monitor and determine if the problem was mechanical or associated with t - feedwater instrumentation. An investigation disclosed a malfunction _of the Feedwater Master Level Controller circuit board. On December 7, 1989, l

reactor power was reduced to approximately 85% for control rod pattern adjustments and the Feedwater Master Level _ Controller circuit board was replaced. The power reduction lasted approximately 16.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

On December 30, 1989, a manual scram was initiated due to loss of Plant Service Water (PSW) (LER 89-019). While operating at approximately 824 reactor power, several radial well pumps began to cycle on and off due toi a malfunction of the Microwave Control system. Ultimately, the bus breakers tripped and failed to reset. Reactor power was reduced and the manual scram was initiated. PSW was restored by disconnecting the controlling inputs to the bus breaker controls and restoring power locally. The generator was synchronized on January 1, 1990 at 0004. Total outage duration was 30.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Long term corrective actions being considered include periodic.

equipment checks'and design enhancements.

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MAIN GTEAM SAFETY RELIEF VALVE CHALLENGES c

y Date of Occurrence: December 30, 1989

. Plant Operating Condition:

i-b Rx Thernal Power 82.8% Rx Pressure (psig)'1000 Rx Mode 1-ff L 'Rx Power (MWE) 1008 Rx Temperatures 540"F

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[ Humber of mainsteam line SRVs: 20 Number of.SRVs affected by event: 12 I

Narrative:.

r , on December 30, 1989,- a manual reactor scram was initiated as a result of loss

'! 1 Plant Service Water (PSW). The Main Steam Isolation Valves were closed in

, ,accordance with the loss of PSW off-normal Event Procedure. A high pressure-reactor scram signal and'ATWS/ARI initiation signal were received.following-the MSIV closurec. Maximum reactor pressure was 1087 psig.' Twelve SRVs were manually cycled one at a time to maintain reactor pressure at the desired pressure range.

SRV B21F047L was cycled a total of thtoe times. The following SRVs were cycled twice eacht 1B21F041F, IB21F04.;C,1B21F041D, IB21F051F,1B21F041A,.

1B21F051C, 1B21F047D, IB21F051K, 1B21F041G, 1B21F047H, and 1B21F051B.

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i.,, .-f,t GGNS Unit 1 Annual Report i

- Man-REM Exposure - 1989

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< This section~contains a tabulation of the number _of station, utility and other personnel receiving exposures greater than 200 mram/yr and their associated i: man-rem exposure according to work and job function.. Also included is a-o tabulation of the' number of personnel by exposure range.

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<' .. PERSDINEL M0 MM-REM PY #0RK M0 DUTY FUNCil~1 FINAL EO OF THE YED REPDR1 F~31989

, NUSER DF PERSDNNEL DVER 100 MREt TDIAL MM4 TEM

'$TATIDN UllLifY CONTRACT NDRKEAS $1A110N UTill1Y COWikAttNDRKERS EMPLOYEES EMPLOYEES MD DTHERS EMPLOYEES EMPLOYEES MD OTERS MAtiDR DPSIBURVEILLMCE

MAlWTENMCE .7 0 2 5.707 0.000 5.936

'OPEkAllDNS $$ 0 2 29.150 'O.000- 0.744 HEALTH PHY$lts 42 0 35 30.464- 0.000- 16.405 BUPERVISOR) 3 0 1. 0.540 0.000 0.969 ENSINEERIN6 1 0 2 0.753 0.000 0.576 RDU11NE MA!WTENHCE .

MAINTENMCE 129 0 374 72.473- 0.000 168.659' DPERAi!DNS  ! -0 2 0.336 0.000 2.736

HEALTHPHYSICS 16 0 17 B.430 0.000 B.012 SUPEKVISDRY l 0 10 ~0.174 0.000 3.274 EN61NEERIN6 2 0 4 1.204 0.000 1.353

!]N-SERVICEINSPEC110W ..

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= MAlW1ENMCE 0 0 33 0.251 DPERAi!DNS 11 0 3 3.B31 0.000 1.062 HEALTHPHYSICS 0- 0 0 0.000 0.000- 0.005 BUPERVISORY 5 6 76 1.991 0.000 42.067 ENGINEERIN6 0 0 3 0.000 0.000. 1.637-7, SPECIAL MAINTENANCE (note 11 MAlWTEh4NCE 4 0 100 1.792 0.000 33.429 OPERAllDNS 2 0 t' O.360 0.000 0.265 HEALTHPHYSICS 0' 0 1 0.090 0.000 0.169 SUPERVISORf 0 0 0 0. 04 5 - 0.000 0.447

'[NGINEERING 3 0 6 0.370 0.000 1.66B NASTEPROCESSIN6

'MAINTENMCE 11 0 9 2.B75- 0.000 .4.009.

OPERAi!DNS' 0 0 1 0.040' 6.006 1.055 HEALTHPHYSICS 0' 0 0 0.065' O.000 0.045

SUPERVISORY 0 0 0 0.000 0.000 0.000 ENGINEERINB 0 .0 0 0.000 0.000 0.030 REFUELINS NAINTENMCE 0 0 34 0.235 0.000 10.171 OPERAi!DNS- 0- 0 28 - 0,197 0.000' 10.485 HEALTHPHYSICS 0 0 0 0.000 0.000 0.000 SUPERV150RY  ! 0 1 0.201 0.000 0.125' 1 0 2 0,340 0.000 1.224

._ENGINEERIN6 TDTALS MAINTENANCE 151 0 560 B3.333 0.000 232.191 OPERAT10NS 69 0 43 33.922 0.000 16.347 HEALTHPHYSICS' 50 0 53. 39.057 0.000 24.636

$UPERVISORY. 10 0 BB 2.951 0.000 46.BB2 ENSINEERINS 7 0 17 2.667 0.000 6.409 BRA O TOTAL 295 0 761 161.930 0.000 326.544 Enote 1 See attached descriptions of jobs included under Special Maintenance category.

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.,,8pecial Maintenance Activities Include:

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1. . Modifications,.. inspections, tests, or special preparations to

. refueling equipment.'

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[ !2. Installation and. testing of.the Alternate Decay Heat Removal System.

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3. Special engineering inspections, photography, radiography, etc.7 v

4. Modification and testing of the Control Rod Drive Maintenance Facility.

[: 5.1 - Modification and testing of the post Accident Sanpling system, p.

[" 6. . Suppression Pool cleaning' operations.

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,- 3': . Sunnary of Failed Fuel Indications / Inspections ,

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' , .No' irradiated fuel assembly. visual inspections were performed during the  ;

reporting period; however, fuel reliability data indicated one medium-sized fuel'

. failure. -Offgas analysis is routinely performed to evaluate and trend-this failure.'

j No Technical' 8pecification limits have been' exceeded.

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