ML20086G656

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Monthly Operating Repts for June 1995 for Limerick Generating Station Units 1 & 2
ML20086G656
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 06/30/1995
From: Gallagher M, Henricks D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9507170038
Download: ML20086G656 (12)
v • d • e


Text

Lim ric's Cener: ting Stattra

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Sanatoga, PA 19464 4920

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T.S.6.9.1.6 July 13, 1995

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Docket Nos. 50-352

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50-353 i

License Nos. NPF-39 l

NPF-85 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555

Subject:

Limerick Generating Station Monthly Operating Report For Units 1 and 2 i

Enclosed are the monthly operating reports for Limerick Units 1 and 2 for the month of June 1995 forwarded 4

pursuant to Technical Specification 6.9.1.6.

very truly yours, Michael P. Gallagher Director - Site Engineering drh Enclosures cc:

T. T. Martin, Administrator, Region I, USNRC N. S. Perry, USNRC Senior Resident Inspector LGS W. G. MacFarland, Vice President, LGS l

9507170038 950630 PDR ADDCK 05000352 1

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Docket No. 50-362 Attachment to Monthly Operating Report for June 1996 f

Limerick Generating Station i

Unit 1 June 1 through June 30,1996 1.

Narrative Summary d Operating Exoeriences Unit 1 began the month d June at a nominal 100% of rated thermal power (RTP).

O'1 June 2,1996, at 1617 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.152685e-4 months <br />, power was reduced to 98% RTP due to high turbine backpressure. Power was restored to 100% RTP at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />.

On June 4,1996, at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, power was reduced to 82% RTP for main turbine valve testing t

and a control rod pattom adjustment. Power was restored to 100% RTP at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />.

On June 19,1996, at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />, power was reduced to 98% RTP due to high turbine backpressure. Power was restored to 100% RTP at 2212 hours0.0256 days <br />0.614 hours <br />0.00366 weeks <br />8.41666e-4 months <br /> On June 20,1996, at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, power was reduced due to high turbine backpressure Power was reduced to 94% RTP. Power was restored to 100% RTP on June 21,1996, at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

On June 22,1996, at 1543 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.871115e-4 months <br />, the 1B circulating water pump tripped due to a ground

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overcurrent. This resulted in a decrease in condenser vacuum. Power was reduced to 96 %

RTP in order to recover condenser vacuum. Power was restorad to 100% RTP on June 23, 1996, at 0000 hourt.

Unit 1 ended this operating period at 100% of RTP.

11.

Challanoes to Main ham Safety Relief Valvas i

There were no challenges to the Main Steam Safety Relief Valves during the month of June.

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OVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO. 50 - 352 i

UNIT LIMERICK UNIT 1 DATE JULY 13 1995 COMPANY PECO ENERGY COMPANY DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 MONTH JUNE 1995 DAv AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILv POWER LEVEL (WWE-NET)

(MWE-NET) 1 1049 17 1046 2

1037 18 1045 3

1037 19 1036 4

981 20 1008 5

1051 21 1041 6

1049 22 1037 7

1034 23 1036 8

1037 24 1046 9

1050 25 1040 10 1051 26 1033 11 1041 27 1045 12 1045 28 1049 13 1050 29 1050 14 1050 30 1044 15 1049 16 1045 W

OPERQTING DQTO REPORT t

DOCKET NO. 50 - 352 DATE JULY 13, 1995 COMPLETED BV PECO ENERGY COMPANY DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 OPERATING STATUS 1

UNIT NAME: LIMERICK UNIT 1 NOTES: THERE WERE NO LOAD DROPS l

2. REPORTING PERIOD:

JUNE. 1995 GREATEP THAN 20% THIS MONTH.

3.

LICENSED THERMAL POWER (MWT):

3293 t

4 NAMEPLATE RATING (GROSS MwE):

1092 l

5. DESIGN ELECTRICAL RATING (NET MwE):

1055

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MwE): 1092
7. MAMIMUM DEPENDABLE CAPACITY (NET MwE):

1055 1

8.

IF CHANGES OCCUR IN CAPACITV RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:

9.

POWER LEVEL TO WHICH RESTRICTED. IF ANY (NET MwE):

10. REASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH VR-TO-DATE CUMdLATIvE ti. HOURS IN REPORTING PERIOD 720 4.343 81.4B?

12. NUMBER OF HOURS REACTOR WAS CRITICA.

720.0 4.242.3 68.350.6

13. REACTOR RESERVE SHUTDCwN HOL'R S 0.0 0.0 0.0 14 HOURS GENERATOR ON-LINE 720.0 4.205.8 67.231.3
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAm ENERGY GENERATED (WWH) 2.360.738 13.760.920 208.077.458 17 GROSS ELECTRICAL ENERGY GENERATED (MWH) 776.400 4.486.300 67.670.580
18. NET ELECTRICAL ENERGv GENERATED (WWH) 749.037 4.335.915 64.979.921 PAGE 1 OF 2 w

. l OPERQTING DOTO REPORT (CONTINUED)

DOCCET NO. 50 - 352 DATE JULY 13, 1995 THIS MONTH VR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 96.8 81.5
20. UNIT AVAILABILITY FACTOR 100.0 96.8 81.5

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21 UNIT CAPACITY FACTOR (USING WDC NET) 98.6 94.6 74.7

22. UNIT CAPACITv FACTOR (USING DER NET) 98.6 94.6 74.?
23. UNIT FORCED OUTAGE RATE O.0 0.9 4.1 24_

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):

25. IF SHUTDOWN AT END 05 ]fPORT PERIOD. ESTIM4TED DATE OF STARTUP:
26. UNIT 5 Ih TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 12/19/84 12/22/84 INITIAL ELECTRICITY MID APRIL B5 4/13/85

___~______

CCMMERCIAL OPERATION 15T OTR 86 2/01/8F PAGE 2 OF 2

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 352 UNIT NAME LIMERICK UNIT 1 DATE JULY 13. 1995 REPORT MONTH JUNE. 1995 COMPLETED BY PECO ENERGY COMPANY DAVID R.

HENRICKS REPORTS ENGINEER l

SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 i

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NETHOD OF l LICENSEE ISv5TEMICOMPONENTI CAUSE AND CORRECTIVE ITVPElDURATION REASONISHUTTING DOwNI EVENT l CODE i CODE l ACTION TO NO.i GA'E i (1)l (HOURS)

(2) l REACTOR (3) !

REPORT a (4) l (51 1 PREVENT RECURRENCE I

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66 I 9506C2 l F l 000.0 H

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HC l HTEXCH I REACTOR POWER WAS REDUCED TO 90% DUE TO 4

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1 4

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! REACTOR POWER WAS REDUCED TO B2% FOR 4

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$ MAIN TURBINE VALVE TESTING AND CONTROL 4

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i ROD PATTERN A DJ U ST M E NT.

4 l 000.0 l

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68 l 950619 F

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4 l

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HC l HTEMCH l REACTOR POWER WAS REDUCED TO 98% DUE TO 4

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1 69 ! 950620 l F

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l 4

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HC HTEXCH l REACTOR POWER WAS REDUCED TO 94% DUE TO 4

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i HIGH TURBINE BACKPRESSURE CAUSEO BV 4

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l l WEATHER CONDITIONS.

4 I

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70 ' 950622 F

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A 4

N/A l

HF PUMPMM l REACTOR POWER WAS REDUCED TO 96% DUE TO 4

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1 CIRCULATING WATER PUMP TRIP CAUSED BV 4

l l GROUND OVERCURRENT.

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(4)

  • - FORCED REASON METHOD EXHIBIT G-INSTRUCTIONS S - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE C-REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

D - REGULATORv RESTRICTION 4 - OTHER (EXPLAIN)

FILE (NUREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION F _ ADMINISTRATIVE (5)

G - OPERATIONAL ERROR (EMPLAIN)

H - OTHER(EXPLAIN)

ExMIBIT I - SAME SOURCE i

1 Dockd N2. 50-353 Attachment to Monthly Operating Report for June 1995 Umerick Generating Station Unit 2 June 1 through June 30,1996 1.

Narrative Summary of Operating Experiences Unit 2 began the month of June at a nominal 100% of rated thermal power (RTP).

On June 3,1995, at 0003 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, a planned power reduction commenced in order to remove the main turbine from service to repair an EHC leak at the number 4 combined intermediate valve.

Power was reduced to 25 % RTP by 0510 hours0.0059 days <br />0.142 hours <br />8.43254e-4 weeks <br />1.94055e-4 months <br />. The main turbine was removed from service at 0518 hours0.006 days <br />0.144 hours <br />8.564815e-4 weeks <br />1.97099e-4 months <br /> and retumed to service at 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br />. Power ascension began at 1232 hours0.0143 days <br />0.342 hours <br />0.00204 weeks <br />4.68776e-4 months <br /> and power was restored to 100% RTP on June 4,1996, at 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br />.

On June 5,1996, at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br />, power was reduced to 90% RTP for a control rod pettom adjustment. Power was restored to 100% fiTP on June 6,1995, at 0214 hours0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br /> On June 17,1996, at 0500, a planned power reduction commenced to repair the 48 and 58 feedwater heater dump valves. Power was reduced to 60% RTP by 0541 hours0.00626 days <br />0.15 hours <br />8.945106e-4 weeks <br />2.058505e-4 months <br />. Power ascension began at 1329 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.056845e-4 months <br /> and power was restored to 100% RTP at 1641 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.244005e-4 months <br />.

On June 18,1996, at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, power was reduced to 90 % RTP for a control rod pattom adjustment. Power was restored to 100% RTP at 1749 hours0.0202 days <br />0.486 hours <br />0.00289 weeks <br />6.654945e-4 months <br />.

On June 20,1995, at 1508 hours0.0175 days <br />0.419 hours <br />0.00249 weeks <br />5.73794e-4 months <br />, power was reduced to 97 % RTP due to high turbine backpressure. Power was restored to 100% RTP at 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br />.

On June 25,1995, at 0134 hours0.00155 days <br />0.0372 hours <br />2.215608e-4 weeks <br />5.0987e-5 months <br />, power was reduced to 90% RTP for control rod scram time testing and a control rod pattom adjustment. Power was restored to 100% RTP at 0741 hours0.00858 days <br />0.206 hours <br />0.00123 weeks <br />2.819505e-4 months <br /> On June 26,1996, at 1624 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.17932e-4 months <br />, the 2B reactor recirculation pump / motor generator set trloped Power was reduced to less than 33% RTP per procedure. Power was stabilized at 31.7% RTP.

The cause for the trip is unknown; system monitoring is in progress. Power ascension comrnonced at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> The 2B reactor recirculation pump was started at 0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> and power was restored to 100% RTP on June 27,1996, at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />.

On June 28,1996, at 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br />, power was reduced to 90% RTP for a control rod pettom edjustment. Power was restored to 100% RTP at 1441 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.483005e-4 months <br />.

On June 28,1995, at 1703 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.479915e-4 months <br />, the 2B reactor recirculation pump ran back to minimum speed when power was lost to the 2B feedwater/ reactor recirculation pump uninterruptable power supply. The 2B reactor foodpump locked up due to the signal failure. Reactor power was stablized at 40% RTP with the A and C reactor feedwater pumps in automatic and the 2B reactor feedpump in standby. Power ascension commenced at 2242 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.53081e-4 months <br /> and power was restored to 100% RTP on June 29,1996, at 0540 hours0.00625 days <br />0.15 hours <br />8.928571e-4 weeks <br />2.0547e-4 months <br />.

On June 30,1995, at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br />, power was reduced to 90% RTP for a control rod pattom adjustment. Power was restored to 100% RTP at 0542 hours0.00627 days <br />0.151 hours <br />8.96164e-4 weeks <br />2.06231e-4 months <br />.

Unit 2 ended this operating period at 100% of RTP.

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CM':.aes to Main Swm Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of June.

)

AVERAGE DAILY UNIT POTER LEVEL 4

DOCKET NO. 50 - 353 UNIT LIMERICK UNIT 2 DATE JULY 13. 1995 1

COMPANY PECO ENERGV COMPANY DAVID R.

HENRICMS REPORTS ENGIt:EER SITE ENGINEERING 4

LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 l

MONTH JUNE 1995 DAV AVERAGE DAILY POWER LEVEL DAV AVERAGE DAILY POWER LEVEL (MWE-NET)

(MwE-NET) 1 1118 17 912 2

1110 18 1110 3

473 19

'110 4

1049 20 1097 5

1106 21 1113 6

1117 22 1117 7

1105 23 1117 8

1109 24 1118 i

9 1122 25 1092 e

10 1122 26 861 J

11 1114 27 771 a

i 12 1118 28 914 13 1122 29 1055 14 1118 30 1109 15 1123 4

l 16 1117 I

i

OPERQTING DOTO REPORT DOCKET NO. 50 - 353 DATE JULY 13. 1995 COMPLETED BY PECO ENERGY COMPANY DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING

~

LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 OPERATING STATUS 1

UNIT NAME: LIMERICA UNIT 2 NOTES: THERE WERE 4 LOAD DROPS

.____.___.._.______~_________.__._

2.

REPORTING PERIOD:

JUNE. 1995 GREATER THAN 20% THIS MONTH

3. LICENSED THERMAL POWER (wwT):

3458 DUE TO THE REPAIR OF AN EHC 4

NAMEPLATE RATING (GROSS MwE):

1163 LEAA. REPAIR OF FEEDWATER HEAT-g

5. DESIGN ELECTRICAL RATING (NET MwE):

1115

-ER DUMP WALVES.A RECIRC PUMP l

g 1

6. MAXIMUM DEPENDASLE CAPACITY (GROSS UwE): 1155 TRIP AND RECIRC PUMP RUN BACK.
7. max! MUM DEPENOABLE CAPACITY (NET MwE):

1115 8.

IF CHANGES OCCUR IN CAPACITV RATINGS (ITEM 5 NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:

9.

POWER LEVEL TO wHICH RESTRICTED. IF ANY (NET MWE):

10. REASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH VR TO-DATE CUMULATIVE 11 HOURS IN REPORTING PERIOD 720 4.343 47.999

12. NUMBER 05 HOURS REACTOR WA5 CRITICAL 720.0 3.823.4 43.186.4
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

_~________._

14 HOURS GENERATOR ON-LINE 714.4 3.710.2 42.315.1

15. UNIT RESERVE SHUTDOWN HOUR 5 0.0 0.0 0.0
16. GROSS THERMAL ENERGV GENERATED (MwH) 2.366.669 11.440.141 133.669.724
17. GROSS ELECTRICAL ENERGv GENERATED (MwH) 785.100 3.801.000 44.184.500
18. NET ELECTRICAL ENERGv GENERATED (MwH) 759.339 3.669.356 42.571.556 PAGE 1 OF 2 L

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OPEROTING DOTO REPORT (CONTINUED)

DOCQEV NO. 50 - 353 DATE JULY 13. 1995 THIS MONTH YR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 99.2 85.4 88.2
20. UNIT AVAILABILITV 8 ACTOR 99.2 85.4 88.2 4

21 UNIT CAPACITY FACTOR (USING MDC NET) 94.6 76.2 83.7 j

22. UNIT CAPACITV FACTOR (USING DER NET) 94.6 76.2 83.7
23. UNIT FORCED OUTAGE RATE O.0 2.1 3.3 24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TVPE. DATE. AND DURATION OF EACH):
25. IF 5HUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED 4

INITIAL CRITICALITV 08/12/89 08/12/89 7

INITIAL ELECTRICITY 09/01/89 09/01/89 COMMERCIAL OPERATION 02/01/90 01/08/90

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1 PAGE 2 OF 2 I

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UNIT SHUTDOWNS OND POWER REDUCTIONS DOCCET NO. 50 - 353 UNIT NAME LIMERICK UNIT 2 DATE JULY 13. 1995 REPORT MONTH JUNE. 1995 COMPLETED BV PECO ENERGY COMPANY DAVID R.

HENRICK$

WEPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 l

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l METHOD OF l

LICENSEE ISYSTEulCOMPONENTl CAUSE AND CORRECTIVE 1

lTYPElDURATIONl REASON) SHUTTING DOWN!

EVENT l CODE 1 CODE l ACTION TO NO.1 DATE l (1)! (HOURS)l (2) l REACTOR (3) l REPORT a I (4) l (5) l PREVENT RECURRENCE i

l I

i 1

54 1 950603 l 5 005.6 i

A 4

l N/A I

HA VALVEX l REACTOR POWER WAS REDUCED TO 25% TO 4

l l

l l

l l REMOVE THE MAIN TURBINE FROM SERVICE TO 4

l l

l I

i REPAIR EHC LEAK AT #4 CIV.

A l

f I

I l

i l

l 55 l 950605 1 5 000.0 l

B l

4 i

N/A RB l CONROD i REACTOR POWER WAS REDUCED TO 90% DUE TO 4

l l

l l

l 1 CONTROL ROD PATTERN ADJUSTMENT.

4 i

I i

1 56 l 950617 F h 000.0 A

4 N/A CH VALVEX l REACTOR POWER WAS REDUCED TO 60% TO 4

l l

l l REPAIR THE FEEDWATER HEATER DUMP VALVE.

4 I

l l

I 57 l 9506'8 l 5 000.0 B

4 l

N/A RB CONROD l REACTOR POWER WAS REDUCED TO 90% DUE TO 4

l l

1 l

l CONTROL ROD PATTERN ADJUSTMENT.

4 l

l I

l I

58 l 950620 l F

000.0 H

4 N/A HC l HTEMCH l REACTOR POWER WAS REDUCED TO 97% DUE TO 4

i l

1 l

l HIGH TURBINE BACM PRESSURE CAUSED BV 4

l l

l l

l WEATHER CONDITIONS.

4 I

I I

I I

I i

59 I 950625 i S 000.0 i

B 4

l N/A l

RB l CONROD I REACTOR POWER WAS REDUCED TO 90% DUE TO 4

l l

l l

l l

i CONTROL ROD PATTERN ADJUSTMENT AND 4

l l

1 l

I i

i CONTROL ROD SCRAM TIME TESTING.

4 l

l 1

I i

l 60 1 950626 l F

000.0 i

A 4

i N/A l

CB l PUMPxx REACTOR POWER WAS REDUCED TO 31.7% DUE 4

(1)

(2)

(3)

(4) r - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS 5-SCHEDULED A - EOUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY 5HEETS 50R LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EMPLAIN)

FILE (NUREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION P - ADMINISTRATIVE (5)

G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EXPLAIN)

EXHIBIT I - SAME SOURCE

. ~.. _. _-.-..-

UNIT SHUTDOWNS OND POWER REDUCTIONS DOCGET NO. 30 - 353 j

UNIT NAME LIMERICK UNIT 2 DATE JULY 13. 1995 REPORT MONTH JUNE. 1995 COMPLETED BY PECO ENERGY COMPANY DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICM GENERATING STATION TELEPHONE (610) 718-3772

~

l l

l METHOD OF l LICENSEE l SYSTEM COMPONENTI CAUSE AND CORRECTIVE lTVPElDURATIONl REASON SHUTTING DOwNI EVENT l CODE CODE 1 ACTION TO NO.

DATE l (1)! (HOUR 5)I (2)

REACTOR (3) l REPORT

  • l (4)

(5) l PREVENT RECURRENCE 1

l l

l I TO REACTOR RECIRCULATION PUMP / MOTOR 4

l l

l GENERATOR SET TRIP.

4 I

I I

(1 950628 l 5 000.0 B.

4 l

N/A RB CONROD l REACTOR POWER WAS REDUCED TO 90% DUE TO 4

1

)

l l

l I

i i CONTROL ROD PATTERN ADJUSTMENT.

4 I

i I

I i

I e2 1 950628 i

  • 000.0 A

l 4

l N/A l CB l PUMPA7 i REACTOP POWER WAS REDUCED TO 40% DUE TO 4

l l

I l

l POWER LOSS TO FEEDwATER/ REACTOR 4

l l

l RECIRCULATION PUMP.

4 1

i 63 950630 S

000.0 B

4 N/A l

RB CONROD I REACTOR POWER WAS REDUCED TO 90% DUE TO 4

i CONTROL ROD PATTERN ADJUSTMENT.

4 I

4 l

l l

4 l

l 4

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1 5.6 l

l 1

1 (1)

(2)

(3)

(4) s. FORCEO REASON METHOD EXHIBIT G - INSTRUCTIONS S-SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA l

B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

D-REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (NUREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION q

F _ ADMINISTRATIVE (5) i G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EXPLAIN)

EXHIBIT I - SAME SOURCE 1

4 i

b a

-

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