ML20087F079: Difference between revisions
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| number = ML20087F079 | | number = ML20087F079 | ||
| issue date = 07/31/1995 | | issue date = 07/31/1995 | ||
| title = Monthly Operating Repts for Jul 1995 for Limerick Generating Station | | title = Monthly Operating Repts for Jul 1995 for Limerick Generating Station | ||
| author name = Gallagher M, Henricks D | | author name = Gallagher M, Henricks D | ||
| author affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC | | author affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
Latest revision as of 02:36, 16 April 2020
ML20087F079 | |
Person / Time | |
---|---|
Site: | Limerick |
Issue date: | 07/31/1995 |
From: | Gallagher M, Henricks D PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9508150111 | |
Download: ML20087F079 (11) | |
Text
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' i .. . umorick Generating Station ~ {
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Sanatoga, PA 19464-0920 T.S.6".9.1.6 l August 10, 1995 Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 a
U. S. Nuclear Regulatory Commission ,
Attn: Document Control Desk j 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 July 1995 forwarded i pursuant to Technical Specification 6.9.1.6.
i Very truly yours, ,
Midhael P. Gallagher ^
( Director - Site Engineering drh-Enclosures cc: T. T. Martin, Administrator, Region I, USNRC N. S. Perry, USNRC Senior Resident Inspector LGS l W. G. MacFarland, Vice President, LGS I53100 9508150111 950731 PDR- ADOCK 05000352 R PDR c.
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Attachment to Monthly l Operating Report for . _)
Jtsy 1996 j q
Limerick Generating Station !
Unit 1 - i
~ July 1 through July 31,1996, j 1
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. l.- l Narrative Summary of Operatina Experiences d
s -q
, Unit 1 began the month of July at a nominal 100% of rated thermal power (RTP). j
~i
- On July 4,1996, at 0102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br />, power was reduced to 90% RTP for main . 1 turbine valve testing. Power was restored to 100% RTP shortly thereafter. l 1
- On July 5, 6,13,14,16,16,17,18, 24, 26, 26, 27, 28 and 29,1906, power was ;
reduced slightly due to high turbine backpressure as a result of elevated outside l air temperature. Power was restored to 100% RTP when turbine ' =4- ::N j
,m was retumed to acceptable values. j j
- On July 8,1996, at 1320 bc um, power was reduced to 90% RTP to insert control rod 34-43 in order to supprass power near the suspected fuel leak. Power was : ;
restored to 100% RTP at 1442 hours0.0167 days <br />0.401 hours <br />0.00238 weeks <br />5.48681e-4 months <br /> 1
, - On July 19,1996, at 1642 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.24781e-4 months <br />, the reactor pressure vessel level increased to . .j 42 inches, the C feedwater hester string lantatart and reactor power traces , ;
indicated that power had increased to approximately 110% and decreased to :
. 80%. This was the result of a 1B recirculation motor-generator est perturbation. !
Reactor power was reduced to 90% RTP por procedure._ Power was further {
reduced to 96% NTP and the C feedwater hoster string was retumed to servios.
Power was restored to 97% RTP on July 20,1996, at 0334 hours0.00387 days <br />0.0928 hours <br />5.522487e-4 weeks <br />1.27087e-4 months <br />. ;
I
- On July 20,1996, at 2242 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.53081e-4 months <br />, power was reduced to 75% RTP for control rod ,
hydraulic control unit (HCU) maintenance. Power was further reduced on July l 22,1996, at 070u nours, to 8b5 RTP for condenser waterbox cleaning l Following waterbox cleaning, power was restored to 76% RTP at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />. i HCU maintenance was completed on July 23,' 1996, and power ascension to j 100% RTP began at 2044 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.77742e-4 months <br />. Power was restored to 100% RTP at 0820 l hours on July 24,1996. 1
^1
- - On July 30,1996, at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, power was reduced to 96% RTP for control rod yi exercise testing. Power was restored to 100% RTP, at 0201 hours0.00233 days <br />0.0558 hours <br />3.323413e-4 weeks <br />7.64805e-5 months <br />, on July 31, !
f 1996.
Unit 1 ended this operating period at 100% of RTP. q
- 11. Challenges to Main Steam Safety Relief Valves l d
in l There were no challenges to the Main Steam Safety Relief Valves during the month of July. l o
i
__ _ ._ _ _ _ _ _ . . ~
DVEROGE DOILY UNIT POWER LEVEL '
- 1-DOCKET No. 50 - 352 UNIT LIMERICK UNIT 1
...... ...._- ...=- --
LATE AUGUST 10.1995 COMPANY PECO ENERGY COMPANY DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STA TION TELEPHONE (610) 718-3772 MONTH JULv.1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
.(wwE-NET) (MwE-NET) 1 1036 17 1006 2 1044 18 1019 3 1048 19 1015 4 1036 20 998 5 1027 21 723 6 1028 22 641 +
7 1039 23 791 0 1036 24 1014 ,
9 1051 25 1013 10 1039 26 1001 11 1044 '.# 27 1013 12 1039 28 1005 13 1015 .75 1000 14 981 ' 3'; 1029 15 897 31 1028 16 983
_ _ _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . - . . . - . . - . __ . - , . . _. . . . - ._, . . _ _ . . . - . ~ . . ,-_..-......m _ . ._. -. . ._._ ..___ ., ., .
_-2 1
OPEAATING DATA REPORT *' '
DOCKET NO. 50 - 352 DATE AUGUST 10.1995 COMPLETED BY PECO ENERGY COMDANY DAVID R. HENRICKS REPORTS ENGINEER .*
SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE L610) 718-3772 OPERATING STATUS l 1 UNIT NAME: LIMERICM UNIT 1 NOTES: THERE wERE 2 LOAD DROPS 2, REPORTING PERIOD: JULY. 1995 GREATER THAN 20% THIS MONTH
- 3. LICENSED THERMAL POWER (MWT): 3293 DUE TO CONTROL ROD HYDRAULIC 4 NAMEPLATE RATING (GROSS MwE): 1092 CONTROL UNIT MAINTENANCE AND
- 5. DESIGN ELECTRICAL RATING (NET MwE): 1055 CONDENSER WATER Box CLEANING j
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MwE): 1092 7 MAXIMUM DEPENDABLE CAPACITY (NET MwE): US 8.
IF CHANGES OCCUR IN CAPACITV RATINGS (ITEMS NUMBER 3 THRwUGH 7) SINCE LAST REPORT. GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED. IF ANY (NET MwE):
- 10. REASONS FOR RESTRICTIONS. IF ANY:
l l
THIS MONTH VR-TO-DATE CUMULATIVE 11 MOURS IN 9EPORTING PERIOD 744 5,087 83.231
- 2. NUMBER OF h00R$ REACTOR WAS CRITICAL T44.0 4.986.3 69.094.6
- 13. REACTOR RE!.ERVE SHUTDOWN HOURS 0.0 0.0 0.0 14 HOURS GENERATCR ON-LINE 744.O 4.949.8 67.975.3
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGv GENERATED (MwH) 2.342.750 16.703.670 210.420.208 17 GROSS ELECTRICAL ENERGY GENERATED (MwH) 763.703 5.250.000 62.434.280
- 10. NET ELECTRICAL ENERGY GENERATED (wwH) 735.331 .
5.071.246 65.715.252 l
PAGE 1 05 2
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1 OPEQQTING DATO REPORT (CONTINUED) DOCRET NO. 50 - 952 - 1-DATE AUGUST 10.1995 THIS MONTH VR.TO-DATE CUMULATIVE
-19. UNIT SERVICE FACTOR- 100.0 97.3 81.7 .
- 20. UNIT AVAILABILITY FACTOR -100.0 97.3 81.7 21.'JNIT CAPACITY FACTOR (USING WDC NET) 93.7 94.5 74.8
- 22. UNIT CAPACITY FACTOR (USING DER NET) 93.7 94.5 74.8
- 23. UNIT FORCED OUTAGE RATE O.0 0.8 4.0 24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):
- 25. IF SHUTDOWN AT END OF REDORT PERIOD. ESTIMATED DATE OF STARTUD 26.. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITV 12/19/84 12/22/64 INITIAL ELECTRICITY MID APRIL 85 4/13/85 COMMERCIAL OPERATION IST OTR 86 2/01/86 f
PAGE 2 OF 2
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCCET NO. GO - 352 UNIT NAME LIMERICK UNIT 1 DATE AUGUST 10,1995 REPORT MONTH JULY. 1995 COMPLETED BY PECO ENERGY COMPANY .
DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING .
LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 l l METHOD OF l LICENSEE l SYSTEM COMPONENT! CAUSE AND CORRECTIVE TVPE DURATIONIREASONISHUTTING DOWNi EVENT l CODE CODE l ACTION TO NO. DATE (1) (HOURS)) (2) l REACTOR (3) l REPO9T a ! (4) (5) l PREVENT RECURRENCE I i i l I 71 l 950704 l 5 000.0 i B 4 l N/A HA VALVEA REACTOR POWER WAS REDUCED TO 90% FOR l l l MAIN TURBINE VALVE TESTING.
I i I 7; i 950708 5 000.0 l A 4 i N/A RS CONROD REACTOR POWER WAS REDUCED TO 90% TO l INSERT CONTROL ROD TO SUPPRESS POWER l NEAR THE SUSPECTED FUEL LEAK.
~3 950719 F 000,0 A 4 1-95-003 CB GENERA REACTOR POWER WAS REDUCED TO 95% DUE TO 1B RECIRCULATION M-G SET PERTURBATION.
74 950720 $ 000.0 8 4 1 N/A RD CRDRVE REACTOR POWER wAS REDUCED TO 75% FOR I I I CONTROL ROD HvDRAULIC CONTROL UNIT MAINT 1 i t i i 75 l 950722 S l 000.0 e 4 i N/A i MC HTEXCH l REACTOR POWER WAS REDUCED TO 60% DUE TO
! CONDENSER WATERBOX CLEANING.
I 76 950730 5 000.0 B 4 ! N/A RH CONROD REACTOR POWER WAS REDUCED TO 95% DUE TO 1 CONTROL ROD EXERCISE TESTING.
I I i 1 l : 1 1 i I (1) (2) (3) (4)
- - FORCED REASON ME* HOD EXHIBIT G- INSTRUCTIONS S- SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) * . 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 - REGULATORS RE$TRICTION 4 - OTHER (E*PLAINI FILE (NUREG-0161)
E - OPERATOC TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (S)
G - OPERATIONA. ERROR (ERPLAINf M - OTHER(EAPLAIN) EXHIBIT I - SAME SOURCE
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Docket No. 50453 cn Attachment to Monthly Operating Report for.-
July 1995 Umorick Generating Station Unit 2 July 1 through July 31,' 1995
- 1. Narrative Summary d Operating Experiences Unit 2 began the month of July at a nominal 100% of rated thsemal power (RTP).
- ' On' July 6,13,14,15,17,23,25,26,27,28 ard 29,1995, power was reduced slightly due to high tuttine backpressure as a result of elevated outside air temperature. Power was restored to 100% RTP when turbine backpressure was
. retumed to acceptable values.
- ' On July 17,1995, at 1805 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.868025e-4 months <br />, the 2B reactor recirdion pump tripped due to a spurious high oE temperature spike. Power was stabei zed at 32% RTP and the unit performed the necessary actions for single reactor recirculation pump operation. At 1936 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.36648e-4 months <br />, the 28 reactor recirculation pump was started. Power ascension to 100% RTP began at 2312 hour0.0268 days <br />0.642 hours <br />0.00382 weeks <br />8.79716e-4 months <br />sJ On July 18,1995, at 0325 hours0.00376 days <br />0.0903 hours <br />5.373677e-4 weeks <br />1.236625e-4 months <br />, power was restored to 100% RTP.
- On July 18,1995, at 0503 hours0.00582 days <br />0.14 hours <br />8.316799e-4 weeks <br />1.913915e-4 months <br />., power was radiced to 97% RTP due to a thermal limit indicating greater than one. It was kiter determined that the indicated thermal limit in excess of one was due to a computer malfunction Power was restored to 100% RTP at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.
- On July 30,1995, at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />, power was reduced to 90% RTP for main turbine valve testing. Power was restored to 100% RTP at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />.
Unit 2 ended this operating period at 100% of RTP.
II. Challenges to Mair1 Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of July.
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.. s NhY OPERATING DATA REPORT DOCMET NO. 50 - 353 DATE AUGUST 10. 1995
. . _ _ _ _ _ _ . . . . _ - = . . --_. ... ..
COMPLETED BV PECO ENERGV COMPANY DAVID R. HENRICKS REDORTS ENGINEER -
SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 OPERATING STATUS
- 1. UNIT NAME: LIMERICK UNIT 2 NOTES: THERE WAS 1 LOAD DROP I
___..._.._ .._ .__.___ ___________ g
- 2. REPORTING PERIOD: JULV. 1995 GREATEc THAN 20% THIS MONTH i
- 3. LICENSED THERMAL POWER (MwT): 3458 DUE TO REACTOR RECIRCULATION 4 NAMEPLATE. RATING (GROSS MwE): 1163 PUMD TRIP. l t
- 5. DESIGN ELECTRICAL RATING (NET MwE): 1115
- 6. MAMIMUM DEPENDABLE CAPACITY (GROSS NwE): 1155 7 MAXIMUM DEPENDABLE CAPACITV (NET MWE): 1115
- 8. IF CHANGE 5 OCCUR IN CAPACITV RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONSr
- 9. POWER LEVEL TO WHICH RESTRICTED. IF ANY (NET MwE):
10.-REASONS FOR RESTRICTIONS. IF ANY:
THIS uONTH VR-TO-DATE CUMULATIVE 11 HOURS IN REPORTING PERIOD 744 5.087 48.743
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 4.567.4 43.930.4
- 13. REACTOR RESERVE SHUTDOWN HUURS 0.0 0.0 0.0 14 HOURS GENERATOR ON-LINE 744.0 4.454.2 43.059.1
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROS $ THERMAL ENERGY GENERATED (MwH) 2.536.414 13.976.555 136.206.138
- 17. GROSS ELECTRICAL ENERGY GENERATED (MwH) 841.200 4.642.200 45.025.780
- 18. NET ELECTRICAL ENERGv GENERATED (MwH) 812.705 4.482.061 43.384.261 DAGE 1 OF 2
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-4 OPERQTING DOTA REPORT (CONTINUED) DOCGQT NO. 60 - 353 '
DATE AUGUST 10 1995
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THIS WONTH VR-TO-DATE CUMULATIVE s
- 19. UNIT SERVICE FACTOG 100.0 87.6 88.3 "
- 20. UNIT AVAILA81LITv F ACTOR 100.0 87.6 88.3
- 21. UNIT CAPACITV FACTOR [USING MDC NET) 98.0 79.4 83.9
- 22. UNIT CAPACITV FACTOR (USING DER NET) ~98.0 79.4 83.9
- 23. UNIT FORCED OUTAGE RATE 0.0 1.7 3.3 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): FORECAST 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
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i UNIT SHUTDOWNS G8cD POWER REDUCTIONS . DOCCIET NO. 50 - 353 UNIT NAME LIMERICK UNIT 2 DATE AUGUST 10, 1995 j REPORT MONTH JULY. 1995 COMPLETED By PECO ENERGY COMPANY .*
DAVID R. HENRICKS '
REPORTS ENGINEER SITE ENGINEERING **
LIMERICM GENERATING STATION TELEPHONE (610) 718-3772 I i L l METHOD OF i LICENSEE SYSTEMICOMPONENT) CAUSE AND CORRECTIVE l ITYPE. DURATION REASONjSHUTTING DOWNI EVENT CODE I CODE l ACTION TO NO.! DATE l (1) (HOURS)I (2) l REACTOR (3) l REPORT a I (4) l (5) -l PREVENT RECURRENCE I I I 60 950717 i F 000.0 A I A N/A CB PUMPXA l REACTOR POWER WAS REDUCED TO 32% DOE TO l 1 i 1 28 REACTOR RECIRCULATION PUMD TRIP.
I t t i 65 950718 l r 000.0 A I 4 i N/A I SH INSTRU f REACTOR POwEA WAS REDUCED TO 97% DuE TO l l } i l l A COMPUTER MALFUNCTION INDICATING A l l l THERMAL LIMIT GREATER'THAN ONE.
I 66 950730 S 000.0 B 4 N/A HA VALVEN REACTOR POWER WAS REDUCED TO 90% DUE TO MAIN TURBINE VALVE TESTING.
I l (1) (2) (3) (4)
F - FORCED REASON METHOD EXHIBIT G- INSTRUCTIONS S - SCHEDULED A - EOUIPMENT 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) 0 - REGULATORv #ESTRICTION 4 - OTHER (EXPLAIN) FILE (NUREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F . ADMINISTRATIVE (5)
G - OPERATIONAL ERDOR (EXPLAIN)
H - OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE s
._.-____-__-____.________-_____.m _ _ . . - - - _. 4 - - - , _ -,-w w .- .- ,, . m ,-,,