Text

Monthly Operating Repts for June 1996 for Limerick Units 1 & 2
	ML20115F047
Person / Time
Site:	Limerick
Issue date:	06/30/1996
From:	Gallagher M, Henricks D; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9607170036
	Download: ML20115F047 (12)
	v • d • e

Lirnirick G:nertting Station

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PECO NUCLEAR

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A Uvr or Pl:Co Iwcv S n toga. PA 19464-0920 T.S.6.9.1.6 July 15, 1996 Docket Nos. 50-352 50-353 License Nos. NPF-39 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 Enclosed are the monthly operating reports for Limerick Units 1 and 2 for the month of June 1996 forwarded pursuant to Technical Specification 6.9.1.6.

Very truly yours, b

W0 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 9607170036 960630 PDR ADOCK 05000352 R

PDR l'/0010 o

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Docket No. 50-352 Attachment to M:nthly

{

Operating Report for June 1996 Limerick Generating Station Unit 1 June 1 through June 30,1996 4

i 1.

Narrative Summarv of Ooeratina Exoeriences i

Unit 1 began the month of June at a nominal 100% of rated thermal power (RTP).

On June 6,1996 at 1209 hours0.014 days 0.336 hours 0.002 weeks 4.600245e-4 months , power was reduced to 92% RTP to support scram j

time testing. Power was restored to 100% RTP on June 6,1996 at 1710 hours0.0198 days 0.475 hours 0.00283 weeks 6.50655e-4 months .

i On June 7, through June 11,1996 power reductions were performed due to elevated turbine backpressure. Power was restored to 100% RTP on June 11,1996 at j

0747 hours0.00865 days 0.208 hours 0.00124 weeks 2.842335e-4 months .

j On June 13,1996 at 0931 hours0.0108 days 0.259 hours 0.00154 weeks 3.542455e-4 months , power was reduced to 95% RTP for a rod pattern

}

adjustment. Power was restored to 100% RTP at 1029 hours0.0119 days 0.286 hours 0.0017 weeks 3.915345e-4 months .

i l

On June 14,1996 at 2157 hours0.025 days 0.599 hours 0.00357 weeks 8.207385e-4 months , power was reduced to 98% RTP for main turbine i

valve testing.' Power was restored to 100% RTP at 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months .

On June 15,1996 at 2055 hours0.0238 days 0.571 hours 0.0034 weeks 7.819275e-4 months , power was reduced to_90% RTP for main turbine valve testing. Power was restored to 100% RTP at 2352 hours0.0272 days 0.653 hours 0.00389 weeks 8.94936e-4 months .

On June 17,1996 at 1405 hours0.0163 days 0.39 hours 0.00232 weeks 5.346025e-4 months , power was reduced to 96% RTP due to elevated turbine backpressure. Power was further reduced to 25% RTP at 1805 hours0.0209 days 0.501 hours 0.00298 weeks 6.868025e-4 months and then 1-the turbine was taken off the grid at 2338 hours0.0271 days 0.649 hours 0.00387 weeks 8.89609e-4 months for repair of 220KV switchyard circuit j.

breaker. The turbine was synched to the grid on June 18,1996 at 0633 hours0.00733 days 0.176 hours 0.00105 weeks 2.408565e-4 months and' power was restored to 100% RTP at 2247 hours0.026 days 0.624 hours 0.00372 weeks 8.549835e-4 months .

l l

On June 19,1996 at 0755 hours0.00874 days 0.21 hours 0.00125 weeks 2.872775e-4 months , power was reduced to 80% RTP for a rod pattem

}

adjustment. Power was restored to 100% RTP at 1155 hours0.0134 days 0.321 hours 0.00191 weeks 4.394775e-4 months .

l On June 20,1996 at 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months , power was reduced to 85% RTP for a rod pattern l

adjustment. Power was restored to 100% RTP at 1018 hours0.0118 days 0.283 hours 0.00168 weeks 3.87349e-4 months .

t l

On June 22,1996 at 0007 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , power was reduced to 98% RTP for main turbine stop and CIV testing. Power was restored to 100% RTP at 0238 hours0.00275 days 0.0661 hours 3.935185e-4 weeks 9.0559e-5 months .

On June 22,1996 at 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months , power was reduced to 98% RTP for elevated main turbine back pressure and valve testing. Power was restored to 100% RTP at i

2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months .

Unit 1 ended this month operating at 100% RTP.

11.

Challenoes to Main Steam Safety Relief Valves j

i There were no challenges to the Main Steam Safety Relief Valves during the month of 1

June.

l I

h

AVERAGE DAILY POWER LEVEL DOCKET NO. 50 - 362 UNIT UMERICKUNIT1 DATE JULY 15,1998 COMPANY PECO ENERGYCOMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610)718-3772 MONTH JUNE,1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 1111 17 905 2

1111 18 419 3

1111 19 1077 4

1108 20 1094 5

1106 21 1099 6

1087 22 1092 7

1000 23 1104 8

1082 24 1103 9

1094 25 1103 10 1094 26 1108 11 1098 27 1109 12 1000 28 1105 13 1098 29 1109 14 1006 30 1109 15 1000 16 1007 i

l l

I

OPERATING DATA REPORT DOCKET NO. 50 - 352 DATE JULY 15,1996 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 WAS ONE LOAD DROP

2. REPORTING PERIOD:

JUNE t996 u

GREATER THAN 20% THIS MONTH

3. LICENSED THERMAL POWER (MWT) 3458 DUE TO REPAIR OF 220KV

4. NAMEPLATE RATING (GROSS MWE): _.

1100 SWITCHYARD CIRCUIT BREAKER.

5. DESIGN ELECTRICAL RABNG (NET MWE):., _ _ _

_ 1105

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

1145

'f. 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 RESTRICTIONS,IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720 4,367 91,271

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 3,852.8 75,876.5

13. REACTOR RESERVE SHUTDOWN HOURS 00 0.0 0.0

14. HOURS GENERATOR ON-LINE 713.1 3,548.7 74,548.6

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 2,425,529 11,329,020 231,489,915

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 798,000 3,713,200 75,347,680

18. NET ELECTRICAL ENERGY GENERATED (MWH) 770,000 3,577,000 72,366,562 i

PAGE 1 OF 2

-. ~.. _ _

_..__._._m OPERATING DATA REPORT (CONTINUED)

DOCKET NO.

50- 352 DATE JULY 15,1996 THIS MONTH YR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 99.0 %

81.3 %

81.7 %

20. UNIT AVAILABILITY FACTOR 99.0 %

81.3 %

81.7 %

21. UNIT CAPACITY FACTOR (USING MDC NET) 96.9 %

74.9 %

75.0 %

22. UNIT CAPACITY FACTOR (USING DER NET) 96.9 %

74.9 %

75.0 %

23. UNIT FORCED OUTAGE RATE 1.0 %

1.7 %

4.2 %

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 12/19/84 12/22/84 INITIAL ELECTRICITY MtD APRIL 85 04'13/85 CONNERCIAL OPERATION IST QTR 86 02/01/86 PAGE 2 OF 2

UNIT SHUTDOWNS AND POWER REDUCTIONS ~

r DOCKET NO. 50-352 UNITNAME LIMERICKUNIT1 DATE JULY 15,1998 i

COMPLETED BY PECO ENERGY COMPANY

)

DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION REPORT MONTH JUNE.1996 TELEPHONE (610)7183772 b

f 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 f

121 980808 S

0.0 B

4 N/A RB CRDRVE REACTOR POWER WAS REDUCED TO 92% DUE TO SCRAM TIME TESTING.

122 980613 S

0.0 B

4 WA RB CONROD REACTOR POWER WAS REDUCED TO 95% DUE TO ROD PATTERN ADJUSTMENT.

123 980614 S

0.0 B

4 WA HA VALVEX REACTOR PONER WAS REDUCED TO 96% DUE TO MAIN TURBINE VALVE TESTING.

4 i

124 900615 -

S 0.0 B

4 WA HA VALVEX REACTOR POWER WAS REDUCED TO 90% DUE TO MAIN TUR8tNE VALVE TESTING.

i 125 980617 F

0.0 H

4

- WA HF HTEXCH REACTOR POWER WAS REDUCED TO 98% DUE TO ELEVATED TUR88NE BACKPRESSURE.

i 126 980617 F

6.9 A

4 WA EG CHTBRK REACTOR POWER WAS REDUCED TO 25% AND THE TUR8INE WAS TAKEN OFF THE GRID DUE TO REPAIR OF 220KV SWITCHYARD CIRCUIT BREAKER.

127 900619 S

0.0 B

4 WA R8 -

CONROD

- REACTOR POWER WAS REDUCED TO 80% DUE TO A ROD PATTERN ADJUSTMENT.

t j

128 900620 S

0.0 B

4 WA RB CONROD REACTOR POWER WAS REDUCED TO 85% DUE TO A ROD PATTERN ADJUSTMENT.

E 129 980822 S

0.0 B

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

(1)

(2)

(3)

(4)

{

F-FORCED REASON METHOD EXHISIT G -INSTRUCTIONS S-SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 -MANUAL FOR PREPARATION OF DATA B -MAINTENANCE OR TEST 2-MANUALSCRAM ENTRY SHEETS FOR UCENSEE i

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)

[

i

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-352 UNIT NAME LIMERICK UNIT 1 DATE JULY 15,1996 COMPLETED BY PECO ENERGY COMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICKGENERATING STATION REPORT MONTH JUNE,1996 TELEPHONE (610)71&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 130 960622 S

0.0 B

4 N/A HA VALVEX REACTOR POWER WAS RFDUCED TO 98% DUE TO MAIN TURBINE VALVE TESTING AND ELEVATED TURBINE BACKPRESSURE.

TOTAL HOURS 6.9 (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-MANUALSCRAM ENTRY SHEETS FOR LICENSEE C-REFUELING 3-AUTOMATIC SCRAM EVENT REPORT (LER) 2 D - REGULATORY RESTRICTION 4-OTHER (FXPLAIN)

FILE (NUREG4161)

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

G-OPERATIONAL ERROR (EXPLAIN)

EXHIBlT I-SAME SOURCE H -OTHER (EXPLAIN)

. - - =

Docket No. 50-353 Attachment to Monthly Operating Report for June 1996 i

Umerick Generating Station Unit 2 June 1 through June 30,1996 1.

Narrative Summarv of Ooeratina Exoeriences Unit 2 began the month of June at a nominal 100% of rated thermal power (RTP).

On June 6,1996 at 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months , power was reduced to 82% RTP due to Isophase bus cooling fans tripping. Power was restored to 100% RTP at 1820 hours0.0211 days 0.506 hours 0.00301 weeks 6.9251e-4 months .

On June 7,1996 at 1945 hours0.0225 days 0.54 hours 0.00322 weeks 7.400725e-4 months , power was reduced to 60% RTP for a rod pattern adjustment and main turbine valve testing. Power was restored to 100% RTP on June 09,1996 at 0740 hours0.00856 days 0.206 hours 0.00122 weeks 2.8157e-4 months .

On June 10,1996 at 2135 hours0.0247 days 0.593 hours 0.00353 weeks 8.123675e-4 months , power was reduced to 75% RTP for a rod pattern adjustment and turbine valve testing. Power was restored to 100% RTP on June 11, 1996 at 0844 hours0.00977 days 0.234 hours 0.0014 weeks 3.21142e-4 months .

On June 14,1996 at 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months , power was reduced to 98% RTP for main turbine valve testing. Power was restored to 100% RTP at 2342 hours0.0271 days 0.651 hours 0.00387 weeks 8.91131e-4 months .

On June 22,1996 at 0126 hours0.00146 days 0.035 hours 2.083333e-4 weeks 4.7943e-5 months , power was reduced to 98% RTP for main turbine valve testing. Power was restored to 100% RTP at 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months .

On June 25,1996 at 2028 hours0.0235 days 0.563 hours 0.00335 weeks 7.71654e-4 months , power was reduced to 95% RTP to compensate for reactor level perturbations during feedwater level control trouble shooting. Power was restored to 100% RTP at 2320 hours0.0269 days 0.644 hours 0.00384 weeks 8.8276e-4 months .

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

II.

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

m.

?'

AVERAGE DAILY POWER LEVEL DOCKET NO.60-353 UNIT UMERICKUNIT2 DATE JULY 15,1998 COMPANY PECO ENERGY COMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEfHONE (610)7184772 MONTH JUNE,1998 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 17 1112 1

1127 18 1103 2

1126 19 1115 3

1126 4

1122 20 1117 5

1122 21 1112 6

1077 22 1107 7

1000 23 1115 8

893 24 1115 9

1074 25 1108 l

10 1084 26 1119 11 1088 27 1119 12 1113 28 1113 13 1116 29 1118 j

14 1114 30 1114 15 1113 16 1114 i

~. _

OPERATING DATA REPORT DOCKET NO. 50 - 353 DATE JULY 15,1996 COMPLETED BY PECO ENERGY COMPANY DAVID R. HENRICKS REPORTS ENGINEER i

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

1. UNIT NAME:

LIMERICK UNIT 2 NOTES: THERE WERE TWO LOAD DROPS

2. REPORTING PERIOD:

JUNEJ996 GREATER THAN 20% THIS MONTH

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

3458 DUE TO ROD PATTERN

4. NAMEPLATE RATING (GROSS MWE):

1163 ADJUSTMENTS AND MAIN TURBINE

5. DESIGN ELECTRICAL RATING (NET MWE): _ _ _ _

1115 VALVE TESTING.

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

1155

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 CUMULATIVE

11. HOURS IN REPORTING PERIOD 720 4,367 56,783

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 4,344.0 51,876.8

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 I

14. HOURS GENEF \\ TOR ONONE 720.0 4,2M7 50,870.5

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

6. GROSS THE'

t. ENERGY GENERATED (MWH) 2,441,326 14,681,314 163,027,047

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 815,100 4,872,400 53,950,200

18. NET El'

. RfCAL ENERGY GENERATED (MWH) 787,963 4,716,162 52,019,793 PAGE 1 OF 2 m

-m OPERATING DATA REPORT (CONTINUED) -

DOCKET NO.

50 -353 DATE JULY 15,1996 THIS MONTH YR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 %

96.0 %

89.6 %

20 UNIT AVAILABILITY FACTOR 100.0 %

96.0 %

89.6 %

21. UNIT CAPACITY FACTOR (USING MDC NET) -

96.2 %

96.9 %

85.7 %

22. UNIT CAPACITY FACTOR (USING DER NET) 96.2 %

96.9 %

85.7 %

23. UNIT FORCED OUTAGE RATE

.0 %

2.0 %

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 S 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 06/12/89 INITIAL ELECTRICITY 0001/89 0001/89 COMMERCIAL OPERATION 02/01/90 01/08/90 t

PAGE 2 OF 2 m..

___..___.___._.-_..___.__________..,_.,m 4,,m....-.m.,

_,--,i-,.

__._.m_.

..___m

.m.

UNIT SHUTDOWNS AND POWER REDUCTIONS y'

DOCKET NO. 50-353 I, '

UNITNAME UMERICKUNIT2 DATE JULY 15,1996 COMPLETED BY PECO ENERGY COMPANY DAVID R. HtENRICKS i

REPORTS ENGINEER SITE ENGINEERING

~

UMERICK GENERATir4G STATION REPORT MONTH JUNE 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 118 960006 F

0.0 A

4 N/A ED ELECON REACTOR POWER WAS REDUCED TO 82% DUE TO ISOPHASE BUS COOUNG FAN TRIPPING.

j 119 960007 S

0.0 B

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 80% DUE TO

[

ROD PATTERN ADJUSTMENT AND MAIN TURBlNE VALVE TESTING.

l 120 900610 S

0.0 B

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 75% DUE TO ROD PATTERN ADJUSTMENT AND TURBINE VALVE TESTING.

i 121 900614 S

0.0 B

4 N/A HA VALVEX REACTOR POWER WAS REDUCED TO 96% DUE TO MAIN TURBINE VALVE TESTING.

122 900622 S

0.0 B

4 N/A HA VALVEX REACTOR POWER WAS REDUCED TO 90% DUE TO MAIN TURB!NE VALVE TESTING.

123 900625 F

00 A

4 N/A CH INSTRU REACTOR POWER WAS MEDUCED TO 95% DUE TO TROUBLESHOOTING FEEDWATER LEVEL CONTROL SYSTEM.

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-REFUEUNG 3 - AUTOMATIC SCRAM EVENT REPORT (LER)

D - REGULATORY RES1RICTION 4-OTHER (EXPLAIN)

FILE (NUREG4161)

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

G-OPERATIONAL ERROR (EXPLAIN) "

EXHIBITI-SAME SOURCE H-OTHER (EXPLAIN)

-

ML20115F047

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