ML17345A921

Parts I & II to Performance Indicators for Operating Commercial Nuclear Power Reactors,Quarterly Repts Data Through Mar 1989

ML17345A921
Person / Time
Issue date:	06/30/1989
From:	William Burton, Hill T, Naraine N NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:
Shared Package
ML17345A922	List: ML17345A921 ML20245H781
References
NUDOCS 8906300097
Download: ML17345A921 (11)

Text

~ 3 Part II of II a(z ~~

Performance Indicators for Operating Commercia)

Nuclear Power Reactors Part II quarterly Report, June 1989 Data through I'1arch 1989 Office for Analysis and Evaluation of Operational Data hi lliam Burton Tracey Hill Neil Naraine Samuel Pett',john Stepnen Ster n

i.K;URE, 4.102 O~RZDZCISIOijAi TURKEY POINT 3

87-2 to 89-1 abdicator L&QQQd'aer Plait Average Crit>cal mrs 4 Qual'ter MavlAg Average I. Automatic Scrams.lfhile Critical 2i Safety System Actuations Iz.

<<C A2 C

r 7/

1

/

~)

!'1.

'. /

YXO 1750 <<a eao a 1250 I 1XO 7M cp 500 0

CJ 4l p ),2 O$

~

$ S'

~NO

~00 ~

1750 <<a eaa ol 1000 750

$5 0

57 2 67-5 67~ 68 1 M 2 MM~ 89 Year Quater 57>>2 87< 67~ 68

'1 66 2 MMM~ 69 Year Quarter

3. Significant Events

4. Safety System Failures 4

<<C w2 87287287~S8 18S 268 585469 1

Year - Quarter S7 2 57 5 87~ 85-1 88 2 MM 85~ 89 1

Year Quarter tN

..J la 0 60 <<

v5 20 <<

4

5. Forced Outage Rate (x)

SS 15I ii 99 57 257M87~SS 165'2~~891 Year>> Quarter F

g e56 O 4 g e K,~ 2 "5

i3. Equipment Forced Outages/

IQOO Critical Hours 6.27 Ax 1+I 0.81 57-2 57 5 87~ 88 1 M 2 M-2 Ma 89 1

Year Quarter

!4761

7. Radiation Exposure 26 k k, 2250 g me~

1750 CCN co usa I X!00 750 g

500 0

57 2 87 2 57

+ M 1 85 2 M S 86-4 69 1

Year Quarter 220

FIGURE 4.102 PRWCISIONAL TURKEY POINT 3: Trends Per Torrnance Indicators Declined Imoroved

1. Automatic Scrcrns While Critical (2 Qtr. Avg end 89-1)

2. Safety System Actuotions (2 Qtr. Avg end 89-1)

3. Significant Events (2 Qtr. Avg end 89-1)

M.97 L91

4. Safety System Failures (2 Qtr. Avg end 89-1)

OA5

5. Forced Outaae Rate (2 Otr. Avg end 89-1)

6. Equipment Forced Outcces/1000 Crit. Hrs.

(2 Gtr. Avg ena h9-1)

-527 2.5-2.0-1.5 -1.0 M.5 0.0 0.5 1.0 1.5 2.0 2.5 Deviations from Previous 4 Otr. Plant Means (Measurea in Stanaard Deviations)

TURKEY POINT 3: Deviations from Old r Plant Means

. 1'orrnance Inciicators Below Avg. Pe.i.

Above Avg. Peri.

1. Automatic Scrams While Criticcl (4 Otr. Avg end 89-1) g>

0.~

2. Scfety System Actuctions (4 Otr. Avg end 89-1)

3. Sianificont Events (4 Qtr. Avg end 89-1)

M.08

4. Scfety System Failures (4 Qtr. Avg end 89-1) 1.45

5. Fcrced Outcae Rate (4 Qtl'. Avg end 89-1) QQQ

-2.65

6. Equipment Forced Outaaes/1000 Crit Hrs.

(4 Gtr. Avg ena 89-1) ~XZQ

-35.e9

-2,5-2.0-1.5 -1.0-0.5 0.0 0.5 1,0 1.5 2.0 2.5 Deviations from Older Plant Means (Measured in Stanaard Deviations) 221

FIGURE 4.103 PHEBZCISII.OqA TURKEY POINT 4

87-2 to 89-1 QZZgg haicator LQQepd Oitter Plant Average Critical Hers 4 Oucrter Moving Average i,,rgutccnatic,Scrams

.1fhile Criticak,

....... Q.:Safety.System. Actuations..

I

)2 J':

///

V

/

t 1>> '.

~

87 2 57 5 57~ 85 1 85 2 85 5~ 69 1

Yeor - Oucrter 2CCD 1750

~+

~

ce 1250 1000 750., u 5CO 0

u rt o w2 d7-2 57 5 87~ 66 1 66 2 65 5 M~ 89 Year - Oucrter

~>>r 2000 ~

1750 o

~

ttt 1259 XXO 750.u c5 500 0

3. Significant Events

4. Safety System Failures 4

c $ 5 trt 4l C

0

.) I'5 O

ma 6'7 2 67 5 87~ 88 1 M-2 85 5 M~ 89 I

Yeor - Ouarter 87 287 587-488~185 288 5&489 1

Year - Oucrter 8-" ~)

'ts w CP

5. Forced Outage Rate (s) 57 F

ob

6. Equipment Forced Outages/

i000 Critical Hours t01 1rd 0 rb gM%x>> rc 87 2 d7 S 57~ M I 65 2 85 5 M~ 89 1

Yeor - Oucrter 57 2 57-5 67~ 85 1 85 2 M-5 M~ 89 1

Yeor Oucr ter

7. Radiation Exposure g rr

~ co

)t 0 'et

~X 50Z 52 26 s.,NA 1

Z~o Q 2000 17M 1250

%00 750 u

MO 2A 43 0

87 2 57 5 d7 4 85 1 65 2 M-5 Qh4 69 1

Yeor Ouarter 222

FIGURc. 4.103 PHZDI SIGNAI.

TURKEY POINT 4: Trends Performance Inaicators Deciined Improved

1. Automatic Scrams While Critical (2 Otr. Avg ena 89-1)

2. Safety System Actuoticns {2 Qtr. Avg end 89-1)

3. Significant Events (2 Qtr. Avg end 89-1)

4. Safety System Failures (2 Otr. Avg end 89-1) l.73

5. Forced Outage Rate

{2 Otr. Avg end 89-1)

6. Equipment Forcea Outcces/1000 Crit. Hrs.

(2 Gtr. Avg end 89-1) ]

L43

-2.5-2.0-1.5 -1.0 M.5 0.0 0.5 1.0 1.5 2.0 2.5 Deviations from Previous 4 Otr. Plant Means (Measurea in Standard Deviations)

TURKEY POINT 4: Deviations from Older Plant Means Pe. formance Inaicators Be!ow Ava. Perf.

Above Avg. Perf

1. Autorna:ic Scrams While Critical (4 Qtr. Avg ena 89-1!

2. Safety System Actuations (4 Qtr. Avg end 89-1)

3. Significcnt Events (4 Otr. Avg end 89-1)

4. Safety System Failures (4 Qtr. Avg ena 89-1)

-tps

5. Forced Outage Rote (4 Qtr. Avg end 89-1)

M.l3

6. Equipment Forced Outcc s/1000 Crit. Hrs.

(4 Qtr. Avg end 89-1) a.n 2.5-2.0-15 -10M,5 00 0.5 1.0 L5 2.0 2.5 Deviations from Older Plant Meons (Measured in Standard Deviations) 223

fp TABLE 9 ~ 102 TURKEY POINT 3

PI EVENTS FOR 88-2 PREDECISIONAL SSF 05/13/88 LER¹ 25088008 50.72¹:

12278 POMER:

100 SYSTEM:

RESIDUAL HEAT REMOVAL SYSTEM (PWR)

[SPECIAL NOH-Ei IS CODE DESC:

POTEHTIAL FOR LACK OF ADEQUATE NPSH TO RHR,CONTAINMENT SPRAY, AND HPSI PUMPS IF RHR TAKING SUCTION FROM CONTAINMEHT SUMP AND OTHER PUMPS TAKIHG SUCTION OFF RHR (PIGGYBACK) DURING POST LOCA COND IT IONS.

SSF 05/29/88 LER¹ 25088011 50.72¹:

12430 POWER:

100 SYSTEM:

EMERGENCY ONSITE POWER SUPPLY SYSTEM (DIESELS)

DESC:

LOCKED CLOSED VALVE DISCOVERED IH DIESEL FUEL OIL SYSTEM. MITH THIS CONDITIOH THE DIESELS WOULD HAVE BEEN ABLE TO START, BUT MOULD RUN FOR ONLY EIGHT HOURS.

PI EVENTS FOR 88-3 SSF 08/22/88 LER¹ 25088018 50.72¹:

13256 PNIER:

100 SYSTEM:

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM DESC:

POTEHTIAL LOSS OF BOTH TRAINS OF CONTAINMENT SPRAY,RHR, AND 2/C Sl PUMPS IF AN ACCIDENT WAS TO OCCUR DURING PERFORMANCE OF THE MONTHLY ECCS VALVE CYCLING PROCEDURE.

PROCEDURE IH ERROR-SSF 09/13/88 LER¹ 25088021 50'2¹:

POWER:

100 SYSTEM:

LOW TEMPERATURE/OVERPRESSURE SYSTEM (SPECIAL NON EIIS CODE

~

DESC:

STROKE TIME OF PORVS (LTOP) EXCEED THE AS SPECIFIED TECH ~ SPEC.

BASIS EVALUATION TIME. DESIGN BASIS OPENING TIME MAS NOT MET.

INADEOUATE DESIGN REVIEW PROCESS.

SSF 09/20/88 LER¹ 25088022 50.72¹:

13720 POMER:

100 SYSTEM:

EMERGENCY ONSITE POWER SUPPLY SYSTEM (DIESELS)

DESC:

THE "B" DIESEL GENERATOR

'MAS OUT OF SERVICE FOR PLANNED MAINTENANCE. THE "A" DIESEL GENERATOR MAS DECLARED OOS DUE TO EXCESSIVE FUEL INLET PRESSURE, FILTER REPLACEMENT INTERVAL HAS BEEN SHORTEHED.

PI EVENTS FOR 88-4 POWER:

0 SSF 10/13/88 LER¹ 25088025 50.72¹:

SYSTEM:

ESSENTIAL SERVICE WATER SYSTEM DESC:

A POTENTIAL INTERACTION BETMEEH THE EDG SEOUENCER AND ESM SYSTEM DISCOVERED. IF "A" TRAIN ESW TRIPPED AND "B4 TRAIN WAS ALREADY RUNNING, "C"TRAIN ESM PUMP. MOULD START AND OVERLOAD EDG.

PI EVENTS FOR 89-1 SSF 01/10/89 LER¹ 25089001 50.72¹:

14/55 POWER:

0 SYSTEM:

ESSENTIAL SERVICE WATER SYSTEM DESC:

AH EMERGENCY SOURCE OF PO'MER WAS NOT AVAILABLE TO THE RHR SYSTEM. "B" EDG MAS INOPERABLE FOR TESTING WHEN THE 3A INTAKE COOLING 'MATER PUMP

'MAS SECURED.

157

~LE 9 ~ 102 (CONT. )

<<RKEY XOZNT 3 (CONT.)

PREDZCTSZONAL PX EVENTS FOR 89-3.

(CONT ~

)

SE 01/16/89 LER¹ 50.72¹:

14512 POMER:

0 OESC:

LICEHSEE FOUHO LEAKS IH 3 REACTOR CORE THIHBI.E GUIDE TUBES SCRAM 02/10/89 LER¹ 25089004 50.72¹:

14714 POUER:

0 DESC:

IMADEQUATE PROCEDURE OID HOT IOEHTIFY MHILE THE REACTOR MAS CRITICAL.

Y PROBLEM HHEH TESTIHG TURBIHE OHL E OHLIHE OR OFFLIHE CAUSIHG THE SCRAM 158

TABLE 9 ~ 103 TURKEY POINT 4

PREDECISIONAL PI EVENTS FOR 88-2 05/13/88 LER¹ 25088008 50.?2¹:

122?8 POWER:

100

=M:

RESIDUAL HEAT REMOVAL SYSTEM (PWR)

(SPECIAL HON-EIIS CCDE

POTEHTIAL FOR LACK OF ADEOUATE NPSH TO RHR, CONTAINHENT SPAY, ANO HPSI PUMPS IF RHR TAKING SUCTION FROH COHTAINHENT SUMP AND OTHER PUMPS TALING SUCTICN FROH RHR (PIGGYBACK) DURING POST LOCA COND ITIONS 05/29/88 LER¹ 25088011 50.72¹:

12430 PO'WER:

100

-H:

EHERGENCY OHSITE POWER SUPPLY S'YSTEH (OIESELS)

I.OCKED CLOSED VALVE DISCOVERED IN DIESEL FUEL OIL SYSTEH.

WITH THIS CONDITION THE DIESELS WOULD HAVE BEEN ABLE TO START BUT WOULD RUH FOR ONLY EIGHT HOURS.

PI EVENTS FOR 88-3 08/19/88 LER¹ Z5188010 50.72¹:

13246 POWER:

100 REACTOR TRIPPED ON I.OW SG LEVEL.

THIS WAS DUE TO PERSONNEL ERROR IN THAT THE OPERATOR SELECTED THE WRONG CHANNEL FOR TESTING.

THE FEEDWATER REGULATIHG VALVE WAS DRIVEN SHUT.

08/22/88 LER¹ 25088018 50.72¹:

13256 POWER:

65

'EH:

ENGINEERED SAFETY FEATURES ACTUATION SYSTEH POTENTIAL LOSS OF BOTH TRAINS OF CONTAINMENT SPRAYS RHRt AND 2/4 SI PUMPS IF AN ACCIDENT WAS TO OCCUR DURING PERFORMANCE OF THE HONTHLY ECCS VALVE CYCLING PROCEDURE.

PROCEDURE IN ERROR.

09/13/88 LER¹ 25088021 50.72¹:

POWER:

100

'EM:

LOW TEMPERATURE/OVERPRESSURE SYSTEH (SPECIAL NON-EIIS CODE

~

STROKE TIHE OF PORVS (LTOP)

EXCEED tHE AS SPECIFIED TECH ~ SPEC.

BASIS EVALUATION TIHE. DESIGN BASIS OPEHIHG TIHE WAS NOT MET ~

INADECUATE DESIGN REVIEW PROCESS.

PI EVENTS FOR 88-4 POWER:

0 10/13/88 LER¹ 25088025 50.72¹:

~"-H:

ESSENTIAL SERVICE WATER SYSTEH

A POTEHTIAL INTERACTION BETWEEH THE EDG SEOUENCER ANO ESW SYSTEM DISCOVERED.

IF "A" TRAIN ESW TRIPPED AND "S" TRAIN WAS ALREADY RUHNING, "C"TRAIN ESW PUMP WOULD START AND OVERLOAD EDG.

PI EVENTS FOR 89-1 02/09/89 LER¹ 25189001 50.72¹:

14704 POWER:

0

'EH:

RESIDUAL HEAT REMOVAL SYSTEH (PWR)

(SPECIAL NON-EI IS CODE RHR PUMP "4A" (THE ONLY OPERASI.E RHR PUMP)

WAS RENDERED TECHNICALLY INOPERABLE WHEN ITS EMERGENCY EDG WAS TESTED.

CAUSED SY HIS.COMMUNICATION BETWEEN OPERATIONS PERSONNEL.

159

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