ML20006F152

Monthly Operating Repts for Jan 1990 for Limerick Generating Station,Units 1 & 2

ML20006F152
Person / Time
Site:	Limerick
Issue date:	01/31/1990
From:	Leitch G, Jerome Murphy PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9002270214
Download: ML20006F152 (12)

Text

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T.S.6.9.1.6 3905047430 PHILADELPHIA ELECTRIC COMPANY i'

LIMERICK GENER ATING ST ATION P. O. DOX A S AN ATOG A, PENNSYLV ANI A 19464 (2 8 5) 3271200, EXT. 3000 i

OR AH AM M. Lt1TCH u............,,......

February 12, 1990 i

Docket Nos. 50-352 50-353 License Nos. NPF-39 3

NPF-85

)

t i

l-U.

S. Nuclear Regulatory Commission Attn:

Document Control Desk l

Washington, DC 20555 I

l

Subject:

Limerick Generating Station Monthly Operating Report For l

Units 1 and 2 i

Enclosed are the monthly operating reports for Limerick Units 1 and 2 for the month of January, 1990 forwarded pursuant to Technical Specification G.9.1.6.

')

i.

s l

Very truly yours,

,4,4*Xan KWM/kk Enclosure cc:- William T. Russell, Administrator, Region I, USNRC

/

T. J. Kenny, USNRC Senior Resident Inspector ll 9002270214 900131 4'

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PDR ADOCM 05000353I'

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pm

o 3905047430

"'"- 5 -3s2 Attachment to Monthly I

Operating Report for

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January 1990 i

Limerick Generating Station r

Unit 1 January 1 through January 31, 1990 1.

Narrative Summary of Operating Experiences j

Limerick Unit 1 began the month of January at a nominal 100%

of rated thermal power.

On January 12, reactor power was reduced to 85% to support a control rod pattern adjustment.

Reactor power was restored to 100% on January 13.

On January 23, reactor power was reduced to 51% to perform SCRAM time testing of twenty-five control rods and to support control rod sequence exchange.

Reactor power was restored to 100% on January 25.

On January 26, reactor power was reduced briefly to 91% to support a control rod pattern adjustment.

Limerick Unit 1 ended the month of January at a nominal 100% of rated thermal power.

i II. Challenccc to Main Steam Safety Relief Valves There were no challenges to the Main Steam Relief Valves during the month of January.

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'.. DOCKET.: NO. 50 352^

DATE FEBRUARY.8. 1990-

.c COWPLETED BV PHILADELPHIA ELECTRIC COMPANY J.-J.

MURPHY.

' REPORTS SUPERVISOR PROJECTS DIVISIONi

.LINERICM GENERATING. STATION

-TELEPHONE (215) 327-1200 EXTENSION 3752-OPERATING STATUS-1 UNIT NAME: LINERICK UNIT 1

'l NOTES: THERE WAS ONE LOAD-l g

g.

2. REPORTING PERIOD:

JANUARY. 1990 1

' REDUCTION GREATER I.

.3. LICEN"ED THERMAL power (wwT):

J3293 i'

THAN 20% THIS MONTH.

g-4 NAMEPLATE RATING (GROSS MwE):

'1138 l

1

5. DESIGN ELECTRICAL RATING (NET MWE): '

1C55 l

{

'l

6. max 1wUM DEPENDABLE CAPACITY (GROSS wwE): 1092 I-

-7. wax!wuw DEPENDABLE CAPACITV (NET WWE):

1055 l

l 8.

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

9. POWER LEVEL TO WHICH RESTRICTED.'IF'ANV.(NET mwE):

10. REASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH VR-TO-DATE CUWULATIVE 744 T44 35.064

=-.872.8

11. HOURS IN REPORTING PERIOD 27

12. NUMBER OF HOURS REACTOR wAS CRITICAL 744.0 744.0

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 14 HOURS GENERATOR ON-LINE 744.0 744.0 27.415.6

15. UNIT' RESERVE? SHUTDOWN HOURS 0.4 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (wwH) 2.410.642

'2.410.642 80.274.082

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 782.810 782.810 25.969.380

18. NET ELECTRICAL ENERGV GENERATED (MwH) 755.879L 755.879 24.812.275 PAGE 1 CF 2 m

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100.0 78.2' 202 UNIT AVAILABILITV FACTOR-100.0:

'100.0t 78.2 12i., UNIT. CAPACITY FACTOR-(USING WDC NET)I 96.3-96.3 67.i

22. UNIT CAPACITY FACTOR (USING DER NET)'

.: 96.3 -'

96.3

.67.1 23.10 NIT FORCED OUTAGE RATE

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0.0 2.9 24;' SHUTDOWNS SCHEDULED OVER NEXT 6 NONTHS (TYPE. DATE: AND DURATION O* EACH):

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25, IF SHUTDOWN AT-END-OF REPORT ~ PERIOD." ESTIMATED DATE OF STARTUpt -

26.-UNITS IN TEST STATUS (PRIOR TO COumERCIAL OPERATION):

FORECAST'

' ACHIEVED-

-INITIAL CRITICALITV 12/19/94 12/22/84' INITIAL ELECTRICITV

WID APRIL 85: 4/13/85-CouwERCIAL OPERATIO**

1ST CTR 86 "2/01/86*

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3 DATE FEBRUARV 8..=- 1990 '

--_ _... 1

_ ~ 990.

COmptETED BY PHILADELPHIA ELECTRIC COMPANY 1

-REPORT WONTH 1 JANUARY.

J. J. NURPHY

- REPORTS SUPERVISOR

^

PROJECTS DIVISION LI#ERICK GENERATING STATION-TELEPHONE (215) 327-1200 EXTENSION 3752.:

-=

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-l l NETHOD OF j LICENSEE' lSYSTEwlCOmPONENTI CAUSE AND CORRECTIVE i

l TYPE l DURATION lREASONISHUTTING DOWNl EVENT l' CODE I CODE l ACTION TO NO.!

DATE l-(1)! (HOURS){

(2) l'REACTfW (3) i REPORT

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F il 4

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! ZZ 1 IZZZZZ 1 LOAD WAS REDUCED TO 15%'TO ACCOWODATE A 1

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CONTROL ROD PATTERN ADJUSTWENT.

10 1 900123'I S

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LOAD WAS REDUCED 49% TO ACCOMOOATE ROD l

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11 900126.

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ZZZZZZ $ LOAD WAS REDUCE 9 9% TO ACCOMOOATE A.

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(2)

(3)

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F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S - SCHEDULED A-EQUIPMENT FAILURE (EXPLAIN).

1 -;WANUAL

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

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

EVENT. REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (NUREG-0161)

E. OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE'

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3905047430 Docket No. 50-353 Attachment to Monthly _

• i Operating Report for January 1990 Limerick Generating Station Unit 2 January 1 through January 31, 1990

}{prtative Summary of Operatina Exoeriences Limerick Unit 2 began commercial operation at 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> January 8, 1990 at 100% of rated thermal. power.

On January 21,-reactor power was reduced to 89% to support Main Turbine control Valve / exercise testing.

Reactor power was restored to 100%. on January 22.

On January 25, reactor power was

- reduced briefly to 90% to accommodate a control rod pattern

. adjustment.

Limerick Unit 2 ended the month of January at a nominal 100%'of rated thermal power, i

Operational events that occurred during the month of January included.

- On January 8, while returning-the Reactor Enclosure HVAC -

system to service, differential pressure ' oscillations occurred.

The

'2A' and

'2C' Reactor. Enclosure Exhaust-

- fans 'were in service end the HVAC. isolation bypass switches had been placed in ' RESET 8 to support HVAC restoration.

Efforts to stabilize Reactor Enclosure.

differential pressure were successful.

Subsequently,-

when the low differential-pressure bypass ruet switches were returned to

' AUTO' per-procedure, a

Reactor Enclosure HVAC isolation occurred.

Investigation revealed that the local handswitches, HS-76-298A-5'and HS-76-298B-5, had been left in the

' TEST' position following. shutdown of. the. Reactor Enclosure HVAC. to repair the

'2B' Reactor Enclosure Exhaust fan.

With:

f these switches in ' TEST',

when the low differential pressure bypass reset switches were taken to " AUTO', an isolation signal was generated. 'The components of the Reactor Enclosure HVAC were correctly aligned per procedure and the system restarted and placed in service.

On January. 12, while placing the

'2A' RWCU Filter Demineralizer in service, a Group III NSSSS isolation Q,,

occurred due to high differential-flow in the RWCU f'-l system.

The isolation was reset to restore the system and investigate the cause of the high differential flow.

While returning the system to service, the

'2A' RWCU Filter Demineralizer was pressurized to check for potential

leakage, this caused a

Group III NSSSS isolatior.

Investigation revealed that the

'2A' Filter Demineralizer inlet line relief valve was found to be opening too quickly, creating a pressure surge which C

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'3905047430 1

L opened ' the. relief valve.

The ' valve stroke time was

' subsequently:- adjusted.

On January 15, the relief valve

~

was replaced and the

'2A'. Filter Demineralizer. was -

. returned:to service without incident..

II.

Challances to Main Steam Safety Relief Valves q

.There were no challenges to the Main Steam Safety Relief-Valves during the month of January, j

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- OPE 2'ATING DATr. CEPORT-

1. ?. s l DOCFET NO. 50 - 353 3

-DATE FEBRUARV 8.

1990.

. COMPLETED BV PHILAOELPHIA ELECTRIC COMPANV J.

J. MURPHV REPORTS SUPERVISOR

PROJECTS DIVISION LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3752 OPERATING STATUS 1.

UNIT NAME: LIMERICK UNIT 2 l NOTES:

THE STARTUP TEST PROGRAM l

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2. REPORTING PERIOD:

JANUARV. 1990

[

COMPLETED AND COMMERCIAL l

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'ICENSED THERMAL POWER (MwT):

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OPERATION WAS DECLARED l

3.

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4 NAMEPLATE RATING (GROSS MwE):

1138 l

AT 0001 HOURS JANUARY 8.

l

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S. DESIGN ELECTRICAL RATING (NET MwE):

1055 i

1990.

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MAXIMUM DEPENDABLE CAPACIT% (GROSS MwE);

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7.

MAXIMUM DEPENDABLE CAPACITV (NET MwE):

l

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8 IF CHAN6ES OCCUR IN CAPACITV RATINGS (ITEMS NUMBER 3 aHROUGH 7) SINCE LAST REPORT. GIVE REASONS:

9.

POWER LEVEL TO wHICH RESTRICTED. IF ANV (NET MwE):

10. RE# SONS FOR RESTRICTIONS. IF ANY:

THIS MONTH VR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 576 576

_ _ _ _ _ _ _5 7 6_ _

12. NUMBER OF HOURS RE AC TOR WAS CRITICAL 576.0 576.0

__ _ _ _ 5 7 6_ 0

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 C.0 0.0

- - _ _ _ _ _5_7_ _6_._0 i4 -OURs bENERATOR ON-LINE SM i SM.0

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGV GENERATED (MwH)'

1.892.047 1.892.047 0$J_,

17. GROSS ELECTRICAL'ENERGv GENERATED (MwH) 639.750 639.750

_ gggg 7)g _

18. NET ELECTRICAL ENERGY GENERATED (MwH) 617.333 617.333

.-_61_7,333-PAGE 1 OF 2 l

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DATE FEBRUARY 8 1990 THIS MONTH VR-TO-DATE.'

CUMULATIVE is. uMIT SERVICE FACTOR

- 100.0 100.0 100.0 4

20. UNIT AVAILABILITY FACTOR

- 100.0 100.0 100.0

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

101.6

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22. UNIT CAPACITY FACTOR (USING DER NET) 10 101.6' l_OJ 6-'

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23. UNIT FORCED OUTAGE' RATE 0.0 0.0 0.0

^24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE 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):

FORCCAST ACHIEVED.

INITIAL CRITICALITV-g((

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,$[Q1/3.1 COMMERCIAL OPERATION 2/_0_1R0__

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1 REPORT WONTHi iJ ANUARV i2 + 1990 "

. COMPLETED BY PHILADELPHIA ELECTRIC COMPANYi "':~.

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). g.j, WURPHY' REPORTS SUPERVISOR-

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PROJECTS' DIVISION 1

6 7"

-. LIMERICK GENERATING STATION'-

TELEPHONE :(215) ' 327-1200 EX. TENSION 3752'

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'1~tMETHOD OF; LICENSEE ilSYSTEMICOMPONENT' CAUSErAND, CORRECTIVE Il

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REASON l SHUTTING.DOWN

' EVENT.

'l CODE'.I

-CODE

-ACTION TO' l.

~l TYPE OURATION

'NO.l 1 OATE' l (1)

.(HOURS)

(2)-l REACTOR-(3).

' REPORT s ' 1 1.

(4) 1.-

.(5)

PREVENT RECURRENCE 1 s.;

7

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-16 900121~

-S.

000.0-.

'B' 4

- )1 : N/A:

l - ' ZZ ZZZZZZ?

-LOAD WAS REDUCED 11% TO'ACCOMODATE

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. MAIN TURSINE CONTROL l VALVI TESTING.

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(2):

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F - FORCED REASON

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METHOD-

. EXHIBIT G - INSTRUCTIONS ;

S -' SCHEDULED A

EOUIPMENT FAILURE (EXPLAIN) 1 - -- MANU AL.

FOR'PREPARA~ ION OF DATA B - MAINTENANCE OR TEST 1

'2 ~~-MANUAL-SCRAM.

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

1 EVENT REPORT (LER)-

D -' REGULATORY RESTRICTION 41-OTHER (EXPLAIN)'

FILE (NUREG-0161)

E. OPERATOR TRAINING +. LICENSE EXAMINATION 1 F -EADMINISTRATIVE-(5)

G - OPERATIONALTERROR '(EXPLAIN)

H - OTHER(EXPLAIN).

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EXHIBIT: I - SAME: SOURCE v

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