ML20117K960

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Monthly Operating Repts for May 1996 for Limerick Generating Station Units 1 & 2
ML20117K960
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 05/31/1996
From: Gallagher M, Henricks D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9606130132
Download: ML20117K960 (13)
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PECO NUCLEAR recO ce-c-eov PO Box 2300 l

A UMt of PfCO ENfRGy Sanatoga PA 19464-0920 l

l T.S.6.9.1.6 June 11, 1996 Docket Nos. 50-352 50-353 l

License Nos. NPF-39 l

NPF-85 l

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 May 1996 forwarded 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 9606130132 960531 PDR ADOCK 05000352 R

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Docket No. 50-352 Attichm:nt to Monthly l

i Operating Report for May 1996 Limerick Generating Station Unit 1 May 1 through May 31,1996 1.

Narrative Summarv of Ooeratina Exoeriences Unit 1 began the month of May at a nominal 100% of rated thermal power (RTP).

On May 10,1996 at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, power was reduced to 97% RTP due to elevated turbine backpressure and for main turbine valve testing. Power was restored to 100%

j RTP on May 11,1996 at 0059 hours6.828704e-4 days <br />0.0164 hours <br />9.755291e-5 weeks <br />2.24495e-5 months <br />.

l On May 11,1996 at 0132 hours0.00153 days <br />0.0367 hours <br />2.18254e-4 weeks <br />5.0226e-5 months <br />, power was reduced to 98% RTP for main turbine 1

valve testing. Power was restored to 100% RTP at 0229 hours0.00265 days <br />0.0636 hours <br />3.786376e-4 weeks <br />8.71345e-5 months <br />.

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On May 11,1996 at 1157 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.402385e-4 months <br />, power was reduced to 85% RTP due to elevated I

turbine backpressure. Power was restored to 100% RTP at 1818 hours0.021 days <br />0.505 hours <br />0.00301 weeks <br />6.91749e-4 months <br />.

On May 17,1996 at 2159 hours0.025 days <br />0.6 hours <br />0.00357 weeks <br />8.214995e-4 months <br />, power was reduced to 98% RTP for main turbine valve and RPS testing. Power was restored to 100% RTP at 2255 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.580275e-4 months <br />.

l On May 18,1996 at 0829 hours0.00959 days <br />0.23 hours <br />0.00137 weeks <br />3.154345e-4 months <br />, power was reduced to 91% RTP for main turbine i

valve and RPS testing Power was restored to 100% RTP power at 1042 hours0.0121 days <br />0.289 hours <br />0.00172 weeks <br />3.96481e-4 months <br />.

l l

On May 19,1996 at 1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br />, power was reduced to 85% RTP due to elevated l

turbine backpressure. Power was restored to 100% RTP on May 21,1996 at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />.

l On May 21,1996 at 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br />, a reactor scram occurred due to a pressure spike during the performance of a MSIV surveillance test. Power was restored to 100% RTP j

May 25,1996 at 0110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br />.

On May 25,1996 at 0919 hours0.0106 days <br />0.255 hours <br />0.00152 weeks <br />3.496795e-4 months <br />, power was reduced to 77% RTP for a control rod l

pattern adjustment. Power was restored to 100% RTP at 1535 hours0.0178 days <br />0.426 hours <br />0.00254 weeks <br />5.840675e-4 months <br />.

l On May 27,1996 at 0111 hours0.00128 days <br />0.0308 hours <br />1.835317e-4 weeks <br />4.22355e-5 months <br />, power was reduced to 86% RTP for minimum generation and control rod pattern adjustment. Power was restored to 100% RTP at 0729 hours0.00844 days <br />0.203 hours <br />0.00121 weeks <br />2.773845e-4 months <br />.

Unit 1 ended this month operating at 100% RTP.

f 11.

Challenoes to Main Steam Safety Relief Valves L

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

[

May, i

i

AVERAGE DAILY POWER LEVEL l

DOCKET NO. 50-352 UNIT UMERICKUNIT1 DATE JUNE 11,1996 COMPANY PECO ENERGY COMPANY DAVID R. HENRfCKS REPORTS ENGINEER SITE ENGINEERING UMERICK GENERATING STATION

~

TELEPHONE (610)7184772 MONTH MAY,1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 1102 17 1101 2

1098 18 1088 3

1100 19 1099 4

1101 20 1004 5

1103 21 983 6

1106 22 0

7 1109 23 0

8 1109 24 393 9

1105 25 1086 10 1088 26 1106-11 1052 27 1079 12 1105 28 1109 13 1110 29 1100 14 1106 30 1108 15 1101 31 1106 16 1096 4

OPERATING DATA REPORT DOCKET NO. 50 - 352 DATE JUNE 11,1996 COMPLETED BY PECO ENERGY COMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENCINEERING LIMERICK GENERATING STATION TELEPHONE (610)718 3772 OPERATING STATUS

1. UNIT NAME:

LIMERICK UNIT 1 NOTES: THERE WERE TWO LOAD DROPS

2. REPORTING PERIOD:

MAY 1996 1

GREATER THAN 20% THIS MONTH,

3. LICENSED THERMAL POWER (MWT) 3458 ONE ASSOC.WITH A REACTOR
4. NAMEPLATE RATING (GROSS MWE):

1100 SCRAM DUE TO A HIGH PRESSURE

5. DESIGN ELECTRICAL RATING (NET MWE):

_1105 SPlKE WHILE CYCLING MSIVs AND

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

1145 CONTROL ROD PATTERN ADJ.

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

1105

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7 ) SINCE LAST REPORT, GIVE REASONS:

C. POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):

10. REASONS FOR RESTRICTIONS,IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURSIN REPORTING PERIOD 744 3,647 90,551
12. NUMBER OF HOURS REACTOR WAS CRITICAL 709.3 2.932.8 75,156.5 13.. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 5
14. HOURS GENERATOR ON-LINE 693.0 2.835.6 73,835.5
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 2,333,323 8,903,491 229.044,386
17. GROSS ELECTRICAL ENERGY GENEPATED (MWH) 770,000 2.915,200 74,549,680
18. NET ELECTRICAL ENERGY GENERATED (MWH) 741,874 2.806,400 71,597,962 PAGE 1 OF 2

y.

OPERATING DATA REPORT (CONTINUED)

DOCKET NO.

50 -352 DATE JUNE 11.1996 j

THIS MONTH YR-TO-DATE CUMULA.

19. UNIT SERVICE FACTOR 93.1 %

77.8 %

81.5 %

20. UNIT AVAILABluTY FACTOR 93.1 %

77.8 %

61.5 %

. 21. UNIT CAPACITY FACTOR (USING MDC NET) 90.2 %

70.5 %

74.8 %

22. UNIT CAPACITY FACTOR (USING DER NET) 90.2 %

70.5 %

74 8 %

23. UNIT FORCED OUTAGE RATE 6.9 %

1.9 %

42 %

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 12f22/84 INITIAL ELECTRICITY MID APRIL 85 04/13/85 COMMERCIAL OPERATION iST QTR 86 0201/86 t

I k

PAGE 2 OF 2

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-352 UNIT NAME UMERICKUNIT1 DATE JUNE 11,1996 COMPLETED BY PECO ENERGY COMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING UMERICK GENERATING STATION REPORT MONTH MAY,1996 TELEPHONE (610)7180772 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 113 960510 F

0.0 H

4 N/A HF HTEXCH REACTOR POWER WAS REDUCED TO 97% DUE TO ELEVATED TURBINE BACKPRESS BECAUSE OF HIGHER THAN NORMAL AMalENT TEMPERATURE.

114 960511 S

0.0 B

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

115 960511 F

0.0 H

4 N/A HF HTEXCH REACTOR POWER WAS REDUCED TO 85% DUE TO ELEVATED TURBINE BACKPRESS BECAUSE OF HIGHER THAN NORMAL AMBIENT TEMPERATURE.

116 960517 S

0.0 B

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

117 960518 S

0.0 B

4 N/A HA VALVEX REACTOR POWER WAS REDUCED TO 91% DUE TO MAIN TURBINE VALVE AND RPS TESTING.

118 960519 F

0.0 H

4 N/A HF HTEXCH REACTOR POWER WAS REDUCED TO 85% DUE TO ELEVATED TURBINE BACKPRESS BECAUSE OF HIGHER THAN NORMAL AMBIENT TEMPERATURE.

119 960521 F

51.0 B

3 1-96-013 CD VALVEX REACTOR SCRAM DUE TO A PRESSURE SPIKE DURING THE PERFORMANCE OF A MSIV SURVEILLANCE TEST.

120 960525 S

0.0 B

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 77% DUE TO CONTROL ROD PATTERN ADJUSTMENT.

(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 (NUREG-0161)

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

G -OPERATIONAL ERROR (EXPLAIN)

EXHIBIT I-SAME SOURCE H - OTHER (EXPLAIN)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-352 UNIT NAME LIMERICK UNIT 1 DATE JUNE 11,1996 COMPLETEDBY PECOENERGYCOMPANY david R.HENRICKS -

REPORTS ENGINEER SITE ENGINEERING UMERICK GENERATING STATION REPORT MONTH MAY,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 121 900527 F

0.0 -

H 4

N/A ZZ 777777 REACTOR POWER WAS REDUCED TO 86% AT THE REQUEST OF THE LOAD DISPATCHER FOR MINIMUM GENERATION AND ROD PATTERN ADJUSTMENT.

TOTAL HOURS 51.0 (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 RESTRICTION 4-OTHER (EXPLAIN)

FILE (NUREG-0161)

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

G -OPERATIONAL ERROR (EXPLAIN)

EXHIBITI-SAME SOURCE H -OTHER (EXPLAIN)

g

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Docket No. 50-353 Attachm:nt to Monthly Operating Report for May 1996 Umerick Generating Station Unit 2 May 1 through May 31,1996 1.

Narrative Summarv of Ooeratino Exoeriences Unit 2 began the month of May at a nominal 60% of rated thermal power (RTP).

i On May 1,1996 at 0928 hours0.0107 days <br />0.258 hours <br />0.00153 weeks <br />3.53104e-4 months <br />, power was reduced to 25% RTP and the turbine was taken off line at 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br /> to perform a control valve electro-hydraulic control system leak repair. The main turbine was synchronized May 2,1996 at 0625 and was tripped at 1017 to replace a backup overspeed relay. Power was restored to 100% RTP on May 4 at 1137 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.326285e-4 months <br />.

On May 5,1996 at 0835 hours0.00966 days <br />0.232 hours <br />0.00138 weeks <br />3.177175e-4 months <br />, power was reduced to 75% RTP for a rod pattern adjustment. Power was restored to 100% RTP at 1658 hours0.0192 days <br />0.461 hours <br />0.00274 weeks <br />6.30869e-4 months <br />.

l On May 11,1996 at 0123 hours0.00142 days <br />0.0342 hours <br />2.03373e-4 weeks <br />4.68015e-5 months <br />, power was reduced to 98% RTP for main turbine valve testing. Power was restored to 100% RTP at 0229 hours0.00265 days <br />0.0636 hours <br />3.786376e-4 weeks <br />8.71345e-5 months <br />.

]

On May 12,1996 at 0212 hours0.00245 days <br />0.0589 hours <br />3.505291e-4 weeks <br />8.0666e-5 months <br />, power was reduced to 87% RTP for main turbine valve testing. Power was restored to 100% RTP at 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br />.

On May 14,1996 at 1033 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.930565e-4 months <br />, a reactor scram occurred from a turbine trip associated with grid instability. Power was restored to 100% RTP May 18,1996 at 0552 hours0.00639 days <br />0.153 hours <br />9.126984e-4 weeks <br />2.10036e-4 months <br />.

'On May 18,1996 at 2325 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.846625e-4 months <br />, power was reduced to 77% RTP for a rod pattern adjustment. Power was restored to 100% RTP May 19,1996 at 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />.

On May 26,1996 at 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br />, power was reduced to 95% RTP for minimum -

generation conditions. Power was restored to 100% RTP at 0825 hours0.00955 days <br />0.229 hours <br />0.00136 weeks <br />3.139125e-4 months <br />.

On May 30,1996 at 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br />, power was reduced to 98% RTP for HCU accumulator trouble. Power was restored to 100% RTP at 1818 hours0.021 days <br />0.505 hours <br />0.00301 weeks <br />6.91749e-4 months <br />.

i -

On May 31,1996 at 1503 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.718915e-4 months <br />, power was reduced to 79% RTP for main turbine valve testing and an HCU repair was performed. Power was restored to 100% RTP at 2202 hours0.0255 days <br />0.612 hours <br />0.00364 weeks <br />8.37861e-4 months <br />.

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

i 11.

Challenoes to Main Steam Safety Relief Valves On May 14,1996 at 10:33 hours, the 2E SRV lifted during a scram. The SRV lifted at approximately 1155 psig and reclosed 8 seconds later at approximately 1035 psig.

E 2

AVERAGE DAILY POWER LEVEL -

DOCKET NO. 50-353 UNIT LIMERICKUNIT2 DATE JUNE 11,1996 COMPANY PECO ENERGY COMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610)7184772 MONTH MAY,1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 270 17 438 2

18 18 1057 3

510 19 1012 4

953 20 1110 5

1083 21 1109 6

1125 22 1109 7

1137 23 1111 8

1129 24 1118 9

1130 25 1132 to 1128 26 1123 11 1122 27 1132 i

i 12 1118 28 1132 13 1135 29 1131 P

14 486 30 1131 15 0

31 1094 16 12 i

m

OPERATING DATA REPORT DOCKET NO. 50 -353 DATE JUNE 11,1996 COMPLETED BY PECO ENERGY COMPANY

~

DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 P

OPERATING STATUS

1. UNIT NAME:

LIMERICK UNIT 2 NOTES: THERE WERE SIX LOAD DROPS

2. REPORTING PERIOD:

__ MAY,1996 GREATER THAN 20% THIS MONTH;

3. LICENSED THERMAL POWER (MWT):

3458 EHC LEAK, FAILED TURBINE TRIP

4. NAMEPLATE RATING (GROSS MWE):

1163 RELAY, ROD PATTERN ADJ (2),

t

5. DESIGN ELECTRICAL RATING (NET MWE):

1115 REACTOR SCRAM, TURBtNE VALVE

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

11_55 l

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

1115

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

THIS MONTH YR-TO-DATE CUMU:.ATIVE

11. HOURS IN REPORTING PERIOD 744 3,647 56,063
12. NUMBER OF HOURS REACTOR WAS CRITICAL 721.0 3.624.0 51,156.8 13 REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 855.7 3,558.7 50.150.5
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 2,306,467 12.239,988 180,585,721 i
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 702,400 4,057,300 53,135,180
18. NET ELECTRICAL ENERGY GENERATED (MWH) 678,894 3.928,199 51,231,830 PAGE 1 OF 2

OPERATING DATA REPORT (CONTINUED)

DOCKET NC.

50 - 3S3 DATE JUNE 11,1996 THIS MONTH YR.TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 88.1 %

97.6 % -

89.5 %

20. UNIT AVAILABILITY FACTOR 88.1 %

97.6 % -

89.5 %

21. UNIT CAPACITY FACTOR (USING MDC NET) 81.8 %

96.6 %

85.5 %

22. UNIT CAPACITY FACTOR (USING DER NET) 81.8 %

96.6 %.

85.5 % '

23. UNIT FORCED OUTAGE RATE 11.9 %

2.4 %

3.3 %

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

EQUIPMENT RELIABlUTY OUTAGE FOR SRV WORK SCHEDULED FOR 9/15/96 USTfNG 5 DAYS.

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

FORECAST ACHIEVED INITIAL CRITICAUTY 08/12/89 08/12/89 INITIAL ELECTRICITY 0901A19 0901A19 -

COMMERCIAL OPERATION 02/01/90 01A)St90 PAGE 2 OF 2

l j

UNIT SHUTDOWNS AND POWER REDUCTIJNS DOCKET NO. 50-353 i

UNITNAME UMERICKUNIT2 i-DATE JUNE 11,1996

[

i COMPLETED BY PECO ENERGY COMPANY l

DAVID R. HENRICKS l

REPORTS ENGINEER SITE ENGINEER!NG UMERICK GENERATING STATION l

REPORT MONTH MAY,1996 TELEPHONE (610)7180772 i

l 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 j

108 960501 F

18 8 A

4 N/A HA VALVEX REACTOR POWER WAS REDUCED TO 25% AND THE TURBINE WAS TAKEN OFF THE GRID DUE TO REoAIR OF TURBINE EHC LEAK l

i 109 980502 F

12.7 A

4 N/A HA INSTRU REACTOR POWER WM REDUCED AND THE i

TURBINE WAS TAKEN 0:F THE GRID DUE TO A FAILED BACKUP OVER', PEED TRIP TEST.

l 110 980505 S

0.0 B

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 75% DUE TO

+

ROD PATTERN ADJUSTMENT.

911 980512 S

00 B

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

l 992 980512 S

0.0 B

4 N/A HA VALVEX REACTOR POWER WAS REDUCED TO 87% DUE TO MAIN TURBtNE VALVE TESTING.

113 980514 F

56.8 H

3 2-9H104 ZZ 777777 REACTOR SCRAM DUE TO TURBINE TRIP CAUSED BY GRID INSTABluTY.

114 980518 S

0.0 B

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 77% DUE TO ROD PATTERN ADJUSTMENT.

115 980526 F

0.0 H

4 N/A ZZ 777777 REACTOR POWER WAS REDUCED TO 95% AT THE REQUEST OF THE LOAD DISPATCHER FOR MINIMUM GENERATION.

t 116 980530 F

0.0 A

4 N/A HA ACCUMU REACTOR POWER WAS REDUCED TO 98% DUE TO (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 (NUREG-0181)

E - OF ERATOR TRAINING + UCENSE EXAMINATION F - ADMINISTRATIVE (5)

G-OPERATIONAL ERROR (EXPLAIN)

EXHIBIT I-SAME SOURCE H -OTHER (EXPLAIN) m.

.m.

.u a.--

mm.

t h

^

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-353 UNITNAME UMERICKUNIT2 DATE JUNE 11,1996 COMPLETED BY PECO ENERGY COMPANY

~

DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING UMERICK GENERATING STATION REPORT MONTH MAY,1996 TELEPHONE (610)7183772 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)

FREVENT RECURRENCE HCU ACCUMULATOR TROUBLE.

117 980531 S

0.0 B

4 N/A HA VALVEX REACTOR POWER WAS REDUCED TO 79% DUE TO MAIN TURBINE VALVE TESTING AND HCU REPA!R.

TOTAL HOURS 88.3 l

(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 (NUREG-0161)

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

G-OPERATIONAL ERROR (EXPLAIN)

EXHIBITI-SAME SOURCE H - OTHER (EXPLAIN)

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