ML20093F444

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Monthly Operating Repts for Sept 1995 for Limerick Generating Station
ML20093F444
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 09/30/1995
From: Gallagher M, Henricks D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9510170403
Download: ML20093F444 (11)
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Sanatoga, PA 19464-0920 T.S.6.9.1.6 October 12, 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

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 September 1995 forwarded pursuant to Technical Specification 6.9.1.6.

I Very truly yours, Mic%selP.Gallagher Dire: tor - 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 170140

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PDR ADOCK 05000352

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Docket No. 50-352 Attachment to Monthly Operating Report for September 1995 Limerick Generating Station Unk1 September 1 through September 30,1995 1.

Narrative Summary of Operating Experiences j

Unit 1 began the month of September in operational condition 4, cold shutdown.

4 l

On September 1,1995 at 0403 hours0.00466 days <br />0.112 hours <br />6.66336e-4 weeks <br />1.533415e-4 months <br />, the mode switch was placed in star:up and the j

Unit was critical at 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />. At 1808 hours0.0209 days <br />0.502 hours <br />0.00299 weeks <br />6.87944e-4 months <br />, the mode switch was placed in Run and -

the Unit was synchronized to the grid at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on September 1,1995.

On September 2,1995 at 0743 hours0.0086 days <br />0.206 hours <br />0.00123 weeks <br />2.827115e-4 months <br />, a Unit shutdown commenced in accordance with Technical Specification 3.0.3 as a result of discovering that both Post-LOCA Hydrogen Recombiner systems were Inoperable due to improper wiring of certain recorders during a recent recorder modification. The main turbine was removed from service at 1140 i

hours and the mode switch was placed in startup at 1409 hours0.0163 days <br />0.391 hours <br />0.00233 weeks <br />5.361245e-4 months <br />. Power reduction j

continued to approximately 6.5% of RTP.

1

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On September 2,1995 at 1950 and 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br />, the B and A Post-LOCA Recombiners were declared operable following corrective actions and testing. Control rod withdrawal a

commenced at 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br /> and, at 2134 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.11987e-4 months <br />, the mode switch was placed in Run.

l The Unit was synchronized to the grid at 0113 hours0.00131 days <br />0.0314 hours <br />1.868386e-4 weeks <br />4.29965e-5 months <br /> on September 03,1995. The Unit was restored to 100% RTP at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on September 4,1995.

I On September 5,1995, at 2113 hours0.0245 days <br />0.587 hours <br />0.00349 weeks <br />8.039965e-4 months <br />, power was reduced to 85% RTP for a control rod pattern adjustment. Power was restored to 100% RTP at 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on September 6, 1995.

.I On September 11,1995 at 1246 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.74103e-4 months <br />, power reduction commenced due to a failed open safety relief valve (SRV). At 1249 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.752445e-4 months <br />, the Unit was manually shutdown since the i

SRV failed to close. An Unusual Event was declared at 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br /> since the SRV failed l

to close after reactor pressure was reduced. The SRV closed when reactor pressure j

reached approximately 407 psig. At 0227 hours0.00263 days <br />0.0631 hours <br />3.753307e-4 weeks <br />8.63735e-5 months <br /> on September 12,1995, the Unusual i

Event was terminated when the B RHR shutdown cooling system was placed in service.

The Unit entered operational condition 4, Cold Shutdown, at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> with reactor coolant temperature at 194 degrees F. During shutdown of the Unit, there were indications of RHR suppression pool suction strainer clogging. As a result, the suppression pool was inspected to determine the cause. The cause of the failed open safety relief valve and RHR suction strainer clogging were investigated and corrective actions taken. Five SRVs were replaced and the suppression pool was thoroughly l

cleaned.

On September 22,1995 at 1636 hours0.0189 days <br />0.454 hours <br />0.00271 weeks <br />6.22498e-4 months <br />, the mode switch was placed in startup and the

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Unit was critical at 2105 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.009525e-4 months <br />. On September 24,1995 at 0608 hours0.00704 days <br />0.169 hours <br />0.00101 weeks <br />2.31344e-4 months <br />, the mode switch 4

was placed in Run and the Unit was synchronized to the grid at 1501 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.711305e-4 months <br /> on September 25,1995, with power at 21% RTP. Power was restored to 100% RTP on September 27,1995 at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />.

On September 28,1995 at 1242 hours0.0144 days <br />0.345 hours <br />0.00205 weeks <br />4.72581e-4 months <br />, power was reduced to 90% RTP for a control rod pattem adjustment. Power was restored to 100% RTP at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />.

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

11.

Challenaes to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of September, 6

---e

AVEROGE DAILY UNIT POWER LEVEL DOCMET NO. 50 - 352 UNIT LIMERICK UNIT 1 DATE SEPTEMBER 11, 1995 COMPANY PECO ENERGV COMPANY DAVID R.

HENRICKS REPGRTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 MONTH SEPTEMBER 1995 DAV AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MwE-NET) 1 33 17 0

2 64 18 0

3 215 19 0

4 848 20 0

5 1024 21 0

6 1047 22 0

7 1038 23 0

8 1043 24 0

9 1038 25 46 10 1050 26 111 11 554 27 985 12 0

28 1040 13 0

29 1054 14 0

30 1055 15 0

16 0

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'OPEQQTING DATA REPORT DOCKET NO '. 50 - 352' DATE SEPTEMBER 11 1995.

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s 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 l NOTES: THERE WERE 2 LO=0 DROPS I

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REPORTING PERIOD: SEPTEMBER. 1995

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GREATER THAN 20% THIS MONTH

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3.

LICENSED THERMAL POWER (WWT):

3293 DOE TO THE POST-LOCA HVDROGEN.

4 NAMEPLATE RATING (GROSS MWE):

1092 RECOMBINER SYSTEMS BEING INOP.

5. DESIGN ELECTRICAL R ATING (NET MwE):

1055 AND A FAILED OPEN SAFETY -

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MwE): 1092 RELIEF VALVE (SRV).

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7. MAXIMUM DEPENDABLE CAPACITV (NET MwE):

1055 l

l 8.

IF CHANGES OCCUR IN CAPACITv RATING 5 (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:

9.

POWER LEVEL TO WHICH RESTRICTED. 18 ANV (NET MWE):

10. REASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH VR-TO-DATE CUMULATIVE 11 HOURS IN REPORTING PERIOD 720 6.551-84.695'

12. NUMBER OF HOURS REACTOR WAS CRITICAL 440.0 5.906.4 70.014.7
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0-

'O.0 14 HOURS GENERATOR ON-LINE 346.3 5.765.4 68.790.9

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 969.710 18.589.822 212.906.360
17. GROSS ELECTRICAL ENERGY GENERATED (MwH) 305.900 6.048.200 69.232.480 18.-NET ELECTRICAL ENERGY GENERATED (MwM) 290.765 5.833.216 66.477.222 PAGE 1 OF 2-

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Op2 RAVING DATA REPOQT'(CONTINUED)'

. DOCCIET - NO ~ GO - 352 -

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_L DATE _ SEPTEMBER-t1,._________....___'

1995 THIS MONTH VR-TO-DATE CUttULATIVE

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19.: UNIT. SERVICE FACTOR.

. 48.1

-88.0 81.2

- 20. UNIT. AVAILABILITY FACTOR

_..'48.1' 88.0 81.2

21. UNIT CAPACITY-FACTOR-(USING MDC NET)-

38.3 84.4-74.4 ~

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22. UNIT. CAPACITY FACTOR (USING bfR NET) 38.3 84.4 74.4

.23'.-UNIT FORCED OUTAGE' RATE 50.4 6.3-4.4 24 SHUTDOWNS. SCHEDULED OVER NEXT 6 MONTHS.(TYPE. DATE. AND DURATION OF EACH):

.t 1 REFUELING OUTAGE. Ssr1EDULED FOR 1/26/96. LASTING 22 DAYS.

25. IFLSHUTDOWN AT.END OF REPORT PERIOD. ESTIMATED DATE OF'STARTUP:
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED

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INITIAL CRITICALITv 12/19/84 - 12/22/84

' INITIAL ELECTRICITv MID APRIL 85 4/13/05 COMMERCIAL OPERATION

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UNIT SHUTDOWN 5 AND POWER REDUCTIONS DOCKET NO. 50 - 352 UNIT NAME LIMERICK UNIT 1

____________________~_..... _

DATE SEPTEMBER 11 1995 REPORT MONTH SEPTEMBER, 1995 COMPLETED By PECO ENERGY COMPANY DAVID R.

HENRICK5 REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 i

l l

l METHOD OF i

LICENSEE

' SYSTEM l COMPONENT l CAUSE AND CORRECTIVE TYPE \\ DURATION REASONlSHUTTING DOWN EVENT CODE I CODE l

ACTION TO NO.

DATE (1)l (HOURS)

(2) l REACTOR (3) l REPORT a (4) l (5) 1 PREVENT RECURRENCE I

I i

81 950901 S

O22.0 A

2 1-95-006 CA PIPEXX

! REACTOR WAS IN A SHUTDOWN CONDITION 4

l (CONTINUED FROM AUGUST) DUE TO LEAKAGE 4

I INTO THE DRvwELL CAUSED BY A MI5 ALIGNED 4

l REACTOR PRES 5URE VE5SEL INSTRUMENT 4

l l

l FLANGE CONNECTION.

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1 82 1 950902 F

013.5 l

A 4

l 1-95-007 I

SE l RECOMB l REACTOR POWER WAS REDUCED TO 6.5% DUE TO 4

l l

1 1

I BOTH DOST-LOCA HVDROGEN RECOMBINER 4

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l

[ SYSTEMS MERE INOPERABLE.

4 I

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83 950905 5

000.0 B l 4

l N/A I

RB CONROD l REACTOR POWER WAS REDUCED TO B5% DUE TO 4

)

l l CONTROL ROD PATTERN ADJUSTMENT.

4 1

1 04 950911 F

338.2 A

2 i

1-95-008 CC VALVEX l REACTOR WAS SHUTDOWN DUE TO A FAILED 4

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I ODEN SAFETY RELIEF VALVE (SRV).

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85 950928 5

000.0 l

B l

4 l

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

l l

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l CONTROL ROD PATTERN ADJUSTMENT.

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t (1)

(2)

(3)

(4) 5 - FORCED REASON METHOD EXHIBIT G-INSTRUCTIONS 5 - SCHEDULED A - EOVIPMENT FAILURE (EXPLAIN)

- MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUA_ SCRAM.

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

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (NUREG-0161)

E - OPERATOD TPa4NING + LICENSE EXAMINATION F - ADMINI STR A TI VE (5)

G - OPERATIONAL ERROR (EPPLAIN)

H - OTHER(EXPLAIN)

EXHIBIT I - SAME SOURCE

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Docket No. 50-353 Attachment to Monthly Operating Report for September 1995 Umerick Generating Station Unit 2 September 1 through September 30,1995 1.

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

On September 2,1995 at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />, a shutdown of the Unit commenced in accordance with Technical Specification 3.0.3 as a result of discovering that a Post-LOCA Hydrogen Recombiner system was Inoperable for greater than Technical Specification limits due to improper wiring of certain recorders during a recent recorder modification. Power reduction continued until 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> and power level at 37% of RTP.

On September 2,1995 at 1824 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.94032e-4 months <br />, the Post-LOCA recombiner was declared operable following corrective actions and testing. Power ascension commenced at 1932 hours0.0224 days <br />0.537 hours <br />0.00319 weeks <br />7.35126e-4 months <br /> and was restored to 100% RTP at 1522 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.79121e-4 months <br /> on September 3,1995.

On September 5,1995 at 0936 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.56148e-4 months <br />, power was reduced to 90% RTP to remove the 60 feedwater heater from service to repair a steam leak on an extraction steam bleeder trip valve. The 6C feedwater heater was removed from service at 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br /> and power 1

was restored to 100% RTP shortly thereafter.

On September 17,1995 at 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br />, power was reduced to 90% RTP for main turbine valve testing. Power was restored to 100% RTP at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />.

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

11.

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

ovERoGE DAILY UZIT POWER LEVEL DOCKET NO. 50 - 353 UNIT LIMERICM UNIT 2

~

DATE SEPTEMBER 11, 1995 COMPANY PECO ENERGV COMPANY DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 MONTH S E P'.' EMB E R 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MwE-NET) 1 1098 17 1109 2

828 18 1119 3

1086 19 1123 4

1114 20 1119 5

1098 21 1115 6

1108 22 1111 7

1110 23 1125 8

1115 24 1122 9

1119 25 1122 10 1123 26 1123 11 1136 27 1126 12 1t08 28 1130 13 1128 29 1129 l

14 1096 30 1129 l

15 1108 t

16 1117 i

OPERQTING DATA REPORT DOCKET NO. 50 - 353 DATE SEPTEMBER 11 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 2 NOTES: THERE WAS 1 LOAD DROP 2.

REPORTING PEPIOD: SEPTEMBER. 1995 GREATER THAN 20% THIS MONTH 3.

LICENSED THERMAL POWER (MwT1:

3458 DUE TO THE POST-LOCA HYDROGEN 4

NAMEPLATE RATING (GROSS MmE):

1163 RECOMBINER SYSTEM BEING 5.

DESIGN ELECTRICAL RATING (NET MWE):

1115 INOPERABLE.

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MwE): 1155 7.

MAXIMUM DEPENDABLE CAPACITY (NET MwE):

1115 l

d.

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

9.

POWER LEVEL TO WHICH RESTRICTED. IF ANV (NET MWE):

10. PEASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH VR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720 6.551 50.207
12. NUMBER OF HOURS R E A CMR WAS CRITICAL 720.0 5.960.8 45.323.6
13. REACTOR RESERVE SHvTDOnN HOURS 0.0 0.0 0.0 14 HOURS GENERATOG UN-LINC 720.0 5.789.1 44.394.0
15. UNIT RESERVE Sdu'DOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MwH1 2.463.382 18.581,479 140.811.062
17. GROSS ELECTRICAL ENERGY GENERATED (MwH) 826.900 6.145.600 4E.529.180
18. NET ELECTRICAL ENERGv GENERATED (Mwn) 796.688 5.928.332 44.830.532 PAGE 1 OF 2

OPERDTING DATA REPORT (CONTINUED)

DOCKET NO. 50 - 353 DATE SEPTEMBER 11 1995 THIS MONTH' YR-TO-DATE CUMULATIVE e

19. UNIT SERVICE FACTOR 100.0 88.4 88.4
20. UNIT AVAILABILITY FACTOR 100.0 88.4 88.4 21.-UNIT CAPACITY FACTOR (USING MDC NET) 99.2 81.5 84.1
22. UNIT CAPACITV FACTOR (USING DER NET) 99.2 81.5 84.1
23. UNIT FORCED OUTAGE RATE O.0 2.5 3.3 24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TVPE, DATE. AND DURATION OF EACH):
25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FvRECAST ACHIEVED INITIAL CRITICALITY 08/12/89 08/12/89 INITIAL ELECTRICITY 09/01/89 09/01/89 COMMERCIAL OPERATION 02/01/90 01/08/90 PAGE 2 OF 2

['

UNIT SHUTDOWNS AMD POWER REDUCTIONS DOCKET Nd. 50 - 353' u------

UNIT NAME LIMERICK UNIT ^2 DATE SEPTEMBER 11, 1995 REPORT MONTH SEPTEMBER, 1995 COMPLETED BY PECO ENERGY' COMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICM GENERATING STATION TELEPHONE (610) 718-3772

~~~- -----------------------------------~~----------------------------------_

~~ ---------

l METHOD OF LICENSEE SYSTEMI COMPONENT CAUSE AND CORRECTIVE l

TVPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO.!

DATE

-(1)

(HOURS)

(2)

REACTOR (3)

REPORT *

(4)

(5)

PREVENT RECURRENCE l

72.

950902 F

000.0 A~

4 l

1-95-007 SE RECOMB REACTOR POWER WAS REDUCED TO 37% UPON 4

1 DISCOVERING A POST-LCCA HYDROGEN 4

RECOMBINER SYSTEM WAS INOPERABLE.

4 1

73 950905 F

000.0 A

4 N/A l

CH HTEXCH REACTOR POWER WAS REDUCED TO 90% TO 4

REPAIR STEAM LEAK ON THE 6C FEEDWATER 4

HEATER.

4 T4 950917 S

000.0 B

4 N/A HA VALVEX REACTOR POWER wAS REDUCED TO 90% DUE TO 4

MAIN TURBINE VALVE TESTING.

4 4

1 4

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(1I (2) t3)

'4)

F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S - SCHEDULED A - EOUIDMENT 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 - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (NUREG-0161)

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

G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EMPLAIN)

EXHIBIT I - SAME SOURCE I

1 i

1 I

l i

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I I

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