ML20116K233

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Monthly Operating Repts for Jul 1996 for Limerick Generating Station Units 1 & 2
ML20116K233
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 07/31/1996
From: Gallagher M, Henricks D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9608140283
Download: ML20116K233 (12)
v • d • e


Text

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Limsrick Gznsrzting Station l

i

  • e PECO NUCLEAR e=~e-"v PO Box 2300 A UNir or PLCO ENtecy Sanatoga, PA 19464-0920 T.S.6.9.1.6 August 13, 1995 Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 U.

S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555 l

Subject:

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

l Enclosed are the monthly operating reports for Lin'erick Units 1 and 2 for the month of July 1996 forwarded pursuant to Technical Specification 6.9.1.6.

l-l Very truly yours,

)b HRG-ee_

l Michael P. Gallagher l

Director - Site Engineering drh

//

Enclosures k3h cc:

T. T. Martin, Administrator, Region I, USNRC N.

S. Perry, USNRC Senior Resident Inspector LGS W. G. MacFarland, Vice President, LGS t

i 9608140283 960731 PDR ADOCK 05000357 l

R PD9 l

l i

.j-l i

Dockit No. 50-352 Attachment to Monthly

}

Operating Report for t

i July 1996 l

Limerick Generating Station Unit 1 July 1 through July 31,1996 j

l.

Narrative Summarv of Operatina Experiences Unit 1 began the month of July 1996 at a nominal 100% of rated thermal power (RTP).

t On July 5,1996 at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />, power was reduced to 98% RTP for main turbine valve testing. Power was restored to 100% RTP at 2350 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94175e-4 months <br />.

On July 8,1996 at 1403 hours0.0162 days <br />0.39 hours <br />0.00232 weeks <br />5.338415e-4 months <br />, power reductions were performed due to elevated i

turt>ine backpressure. Power was restored to 100% RTP on July 9,1996 at 0010 l'

hours.

i l

On July 14,1996 at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />, power reductions were performed due to elevated F

turbine backpressure. Power was restored to 100% RTP on July 15,1996 at 0252 I

hours.

l On July 15,1996 at 0650 hours0.00752 days <br />0.181 hours <br />0.00107 weeks <br />2.47325e-4 months <br />, power was reduced to 98% RTP due to elevated l

turbine backpressure. At 1143 hours0.0132 days <br />0.318 hours <br />0.00189 weeks <br />4.349115e-4 months <br />, power was reduced to 53% RTP to swap steam

}

jet air injector (SJAE) trains. At 1817 hours0.021 days <br />0.505 hours <br />0.003 weeks <br />6.913685e-4 months <br /> the reactor was manually shut down and the e

t main turbine was taken off line to repair unisolable leaks in the SJAE room. On July

)

20,1996 at 0856 hours0.00991 days <br />0.238 hours <br />0.00142 weeks <br />3.25708e-4 months <br /> the reactor was taken critical and on July 21,1996 at 0908 i

hours the man turbine was synchronized to the grid. Power was restored to 100% RTP l

on July 23, at 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br />.

i i

On July 23,1996 at 2236 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.50798e-4 months <br />, power was reduced to 86% RTP for control rod pattom i'

adjustments. Power was restored to 100% RTP on July 24,1996 at 0157 hours0.00182 days <br />0.0436 hours <br />2.595899e-4 weeks <br />5.97385e-5 months <br />.

i On July 25,1996 at 0229 hours0.00265 days <br />0.0636 hours <br />3.786376e-4 weeks <br />8.71345e-5 months <br />, power was reduced to 90% RTP due to 3 bypass valves indicated open. At 0242 hours0.0028 days <br />0.0672 hours <br />4.001323e-4 weeks <br />9.2081e-5 months <br /> the main turbine was tripped due to an automatic l

reactor scram from high flux caused by a turbine control valve closure from an electro-i hydraulic control transient. On July 27,1996 at 1009 hours0.0117 days <br />0.28 hours <br />0.00167 weeks <br />3.839245e-4 months <br /> the reactor was critical and

[

the turbine was synchronized to the grid on July 28,1996 at 0129 hours0.00149 days <br />0.0358 hours <br />2.132936e-4 weeks <br />4.90845e-5 months <br />. Power was j

restored to 100% RTP on July 28, at 2140 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.1427e-4 months <br />.

On July 29,1996 at 0254 hours0.00294 days <br />0.0706 hours <br />4.199735e-4 weeks <br />9.6647e-5 months <br />, power was reduced to 96% RTP for a rod pattom j

adjustment. Power was restored to 100% RTP at 0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br />.

4 On July 31,1996 at 0905 hours0.0105 days <br />0.251 hours <br />0.0015 weeks <br />3.443525e-4 months <br />, power was reduced to 88% RTP for a rod pattom i

adjustment. Power was restored to 100% RTP at 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br />.

Unit 1 ended this month operating at 100% RTP.

1 11.

Challenoes to Main Steam Safety Relief Valves f

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

July.

i

AVERAGE DAILY POWER LEVEL DOCKET NO. 50-352 UNIT LIMERICKUNIT1 DATE AUGUST 9,1996 COMPANY PECO ENERGYCOMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610)7183772 MONTH JULY,1996 DAY AVERAGE DAILY POWER LEVEL DAY' AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 1096 17 0

2 1097 18 0

3 1101 19 0

4 1105 20 0

5 1105 21 123 6

1101 22 850 7

1096 23 1038 8

1076 24 1098 9

1096 25 117 10 1105 26 0

11 1109 27 0

12 1106 28 39 13 1097 29 1001 14 1077 30 1091 15 643 31 1087 16 0

~

OPERATING DATA REPORT DOCKET NO. 50- 352 DATE AUGUST 9,1996 COMPLETED BY 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 TWO LOAD DROPS 1 REPORTING PERIOD:

JULYd996 GREATER THAN 20% THIS MONTH

3. LICENSED THERMAL POWER (MWT). __ _ _ __ _. _ _ _ _. __.

3458 CAUSED BY 2 REACTOR SCRAMS 4 NAMEPLATE RATING (GROSS MWE):

1160 DUE TO A Y-STRAINER STEAM

5. DESIGN ELECTRICAL RATING (NET MWE): _

1105 LEAK AND AN EHC TRANSIENT.

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

11_45

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

11_05

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7 ) SINCE LAST REPORT, GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
10. REASONS FOR RESTillCTIONS,IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744 5,111 92,015 11 NUMBER OF HOURS REACTOR WAS CRITICAL 577.9 4,230.7 76,454.4
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 538.4 4,087.1 75,087.0
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 1,748,796 13,077,816 233,218,711
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 500,400 4,273,000 75,908,000
18. NET ELECTRICAL ENERGY GENERATED (MWH) 539,053 4,116,743 72,908,215 PAGE 1 OF 2

OPERATING DATA REPORT (CONTINUED)

DOCKET NO.

50 - 352 DATE AUGUST 9,1996 THIS MONTH YR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 72.4 %

80.0 %

81.6 %

20. UNIT AVAILABIL11Y FACTOR 72.4 %

80.0 %

81.6 %

21. UNIT CAPACITY FACTOR (USING MDC NET) 65.6 %

73.5 %

74.9 %

22. UNIT CAPACITY FACTOR (USING DER NET) 65.6 %

73.5 %

74.9 %

23. UNIT FORCED OUTAGE RATE 27.6 %

6.1 %

4.4 %

24. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):
25. IF SHUTDOWN AT THE END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATIONS):

FORECAST ACHIEVED INITIAL CRITICALITY 12/11W84 12/22/84 INITIAL ELECTRICITY MID APRIL 85 04/13/85 COMMERCIAL OPERATION IST QTR 86 0201/86 PAGE 2 OF 2

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-352 UNIT NAME LIMERICK UNIT 1 DATE AUGUST 9,1998 COMPLETED BY PECO ENERGY COMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION REPORT MONTH JULY,1996 TELEPHONE (610)718,3772 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO.

DATE (1)

(HOURS)

(2)

REACTOR (3)

REPORT #

(4)

(5)

PREVENT RECURRENCE 131 980705 S

0.0 B

4 N/A HA VALVEX REACTOR POWER WAS REDUCED TO 98% DUE TO MAIN TURBINE VALVE TESTING.

132 900708 F

0.0 H

4 N/A HF HTEXCH REACTOR POWER WAS REDUCED TO 99% DUE TO ELEVATED TURBINE BACKPRESSURE.

133 980714 F

0.0 H

4 N/A HF HTEXCH REACTOR POWER WAS REDUCED TO 99% DUE TO L

ELEVATED TURBINE BACKPRESSURE.

934 980715 F

0.0 H

4 N/A HF HTEXCH REACTOR POWER WAS REDUCED TO 98% DUE TO ELEVATED TURBINE BACKPRESSURE.

135 900715 F

134.9 A

2 N/A HC HTEXCH REACTOR WAS SHUTDOWN TO REPAIR l

UNISOLABLE LEAKS IN SJAE ROOM.

t 136 960723 S

0.0 B

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 86% DUE TO CONTROL ROD PATTERN ADJUSTMENT.

137 980725 F

70.8 A

3 1-96 015 HA VALVEX REACTOR WAS SHUTDOWN DUE TO A ELECTRO-HYDRAUUC CONTROL TRANSIENT OF TURBINE CONTROLVALVES.

t 138 900729 S

0.0 B

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 98% DUE TO ROD PATTERN ADJUSTMENT.

939 900731 S

0.0 A

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 88% DUE TO I

ROD PATTERN ADJUSTMENT.

(1)

(2)

(3)

(4) l F-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-REFUEUNG 3 - AUTOMATIC SCRAM EVENT REPORT (LER)

D - REGUMTORY RESTRICTION 4-OTHER (EXPMIN)

FILE (NUREG4161)

E - OPERATOR TRAINING + UCENSE EXAMINATION F - ADMINISTRATIVE (5) i G - OPERATIONAL ERROR (EXPLAIN)

EXHtBIT I-SAME SOURCE H - OTHER (EXPLAIN)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-352 UNIT NAME LIMERICK UNIT 1 DATE AUGUST 9,1996 COMPLETED BY PECO ENERGY COMPANY '

DAVID R. HENRfCKS REPORTS ENGINEER SITE ENGINEERING UMERICK GENERATING STATION REPORT MONTH JULY,1996 TELEPHONE (610)718-3772 METHOD OF UCENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO.

DATE (1)

(HOURS)

(2)

REACTOR (3)

REPORT #

(4)

(5)

PREVENT RECURRENCE TOTAL HOURS 205.6 (1)

(2)

(3)

(4)

F-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 UCENSEE C-REFUEUNG 3 - AUTOMATIC SCRAM EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4-OTHER (EXPLAIN)

FILE (NUREG4161)

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

G - OPERATIONAL ERROR (EXPLAIN)

EXHIBIT I-SAME SOURCE H - OTHER (EXPLAIN)

Docket N3. 50-353 Attachment t3 Monthly Operating Report for July 1996 Limerick Generating Station Unit 2 July 1 through July 31,1996 1

1.

Narrative Summarv of Operatino Experiences j

Unit 2 began the month of July 1996 at a nominal 100% of rated thermal power (RTP).

On July 6,1996 at 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, power was reduced to 98% RTP for main tubine valve testing. Power was restored to 100% RTP at 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br />.

On July 10,1996 at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, oower was reduced to 90% RTP for a rod pattern adjustment. Power was restored to 100% RTP at 0055 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br />.

On July 13,1996 at 0035 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />, power was reduced to 98% RTP for main turbine valve testing. Power was restored to 100% RTP at 0141 hours0.00163 days <br />0.0392 hours <br />2.331349e-4 weeks <br />5.36505e-5 months <br />.

l On July 13,1996 at 0805 hours0.00932 days <br />0.224 hours <br />0.00133 weeks <br />3.063025e-4 months <br />, power was reduced to 75% RTP for rod pattem adjustment, main steam isolation valve testing, main turbine valve testing and scram time testing. 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 July 27,1996 at 0219 hours0.00253 days <br />0.0608 hours <br />3.621032e-4 weeks <br />8.33295e-5 months <br />, power was reduced to 98% RTP for main turbine valve testing. Power was restored to 100% RTP at 0316 hours0.00366 days <br />0.0878 hours <br />5.224868e-4 weeks <br />1.20238e-4 months <br />.

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

i ll. Challences to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of July.

AVERAGE DAILY POWER LEVEL DOCKET NO. 50-353 UNIT LIMERICKUNIT2 DATE AUGUST 9,1996 COMPANY PECO ENERGY COMPANY DAVID R. HENRfCKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATlON TELEPHONE (610)7180772 MONTH JULY,1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 1113

'17 1092 2

1105 18 1093 3

1114 19 1090 4

1118 20 1103 5

1114 21 1109 6

1114 22 1115 7

1105 23 1118 8

1100 24 1106 9

1096 25 1095 10 1110 26 1104 11 1118 27 1106 12 1114 28 1110 13 1038 29 1117 14 1103 30 1100 15 1001 31 1115 16 1092

. -. _ ~.

OPERATING DATA REPORT DOCKET NO. 50-353 DATE AUGUST 9,1996 COMPLETED BY PECO ENERGY COMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610)718-3772 OPERATING STATUS

1. UNIT NAME:

LIMERICK UNIT 2 NOTES: THERE WAS ONE LOAD DROP

2. REPORTING PERIOD.

JULY,_1996 GREATER THAN 20% THIS MONTH

3. LICENSED THERMAL POWER (MWT): _____

_ _ _. _ _ _3458 DUE TO SCRAM TIME TESTING.

4. NAMEPLATE RATING (GROSS MWE): _ _ _.

_1163

5. DESIGN ELECTRICAL RATING (NET MWE):

1115

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): _

11_55

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

1115

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 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 YR-TO-DATE CUMUt.ATIVE

11. HOURS IN REPORTING PERIOD 744 5,111 57,527
12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 5,088.0 52,620.8
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 744.0 5,022.7 51,614.5
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 2,563,042 17,244,356 165,590,088
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 853,100 5,725,500 54,803,380
18. NET ELECTRICAL ENERGY GENERATED (MWH) 821,336 5,537,498 52,841,129 PAGE 1 OF 2

e OPERATING DATA REPORT (CONTINUED)

DOCKET NO.

50 - 353 DATE AUGUST 9,1998 THIS MONTH YR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 %

98.3 %

89.7 %

20. UNIT AVAILABILITY FACTOR 100.0 %

98.3 %

89.7 %

21. UNIT CAPACITY FACTOR (USING MDC NET) 99.0 %

97.2 %

85.9 %

22. UNIT CAPACITY FACTOR (USING DER NET) 99.0 %

97.2 %

8i9 %

23. UNIT FORCED OUTAGE RATE

.0 %

1.7 %

3.2 %

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

EQUIPMENT RELIABILITY OUTAGE FOR SRV WORK SCHEDULED FOR 9/15/96 LASTING 5 DAYS. REFUELING OUTAGE SCHEDULED FOR 1/2496 LASTING 22 DAYS.

25. IF SHUTDOWN AT THE END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATIONS):

FORECAST ACHIEVED INITIAL CRITICALITY 08/12/89 08/12/89 INITIAL ELECTRICITY 0901/89 0901/89 COMMERCIAL OPERATION 02/01/90 01/08/90 PAGE 2 OF 2

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-353 UNIT NAME UMERICK UNIT 2 DAE AUGUST 9,1996 COMPLETED BY PECO ENERGY COMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING UMERICK GENERATING STATION REPORT MONTH JULY,1996 TELEPHONE (610)718-3772 METHOD OF UCENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO.

DATE (1)

(HOURS)

(2)

REACTOR (3)

REPORT #

(4)

(5)

PREVENT RECURRENCE 124 960706 S

0.0 B

4 N/A HA VALVEX REACTOR POWER WAS REDUCED TO 98% DUE TO MAIN TURBINE VALVE TESTING.

125 960710 S

0.0 B

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 90% DUE TO A ROD PATTERN ADJUSTMENT.

126 900713 S

0.0 B

4 N/A HA VAL'fEX REACTOR POWER WAS REDUCED TO 98% DUE TO MAIN TURBINE VALVE TESTING.

127 960713 S

0.0 B

4 N/A RB CRDRVE REACTOR POWER WAS REDUCED TO 75% DUE TO SCRAM TIME TESTING, ROD PATTERN ADJUSTMENT, TURBINE VALVE TESTING.

128 960727 S

0.0 B

4 N/A HA VALVEX REACTOR POWER WAS REDUCED TO 98% DUE TO MAIN TURBINE VALVE TESTING.

TOTAL HOURS 0.0 (1)

(2)

(3)

(4)

F-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 UCENSEE C - REFUELING 3-AUTOMATIC SCRAM EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4-OTHER (EXPLAIN)

FILE (NUREG-0161)

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

G -OPERATIONAL ERROR (EXPLAIN)

EXHIBIT I-SAME SOURCE H - OTHER (EXPLAIN)

.

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