ML19345D685

Monthly Operating Repts for Nov 1980

ML19345D685
Person / Time
Site:	Peach Bottom
Issue date:	12/10/1980
From:	Alden W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
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ML19345D684	List: ML19345D683 ML19345D685
References
NUDOCS 8012160475
Download: ML19345D685 (9)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE DECEMBER 10, 1980 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH NOVEMBER 1980 OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET) (MWE-NET) 1 1041 17 366 2 1066 18 602 3 1054 19 958 4 1071 20 917 5 854 21 1050 6 446 22 987 7 988 23 731 8 1078 24 927 9 1052 25 1039 10 1078 26 1059 11 1076 27 1060 12 1077 28 1060 13 1077 29 1064 14 121 30 1064 15 0

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801216 0975 1 . ._- ._-- _. - - - _ - . . - - - - - - . --.. - - -- -- - - . .. -

AVERAGE DAILY UNIT POWER' LEVEL DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE DECEM8ER 10, 1980 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH NOVEMBER 1980 DAY AVERAGE DAILY POWER LEVEL DAY ERAGE DAILY POWER LEVEL (MWE-NET) (MWE-NET) 1 857 17 1056 2 1043 18 1052 3 1041 19 1052 4 1034 20 1054 5 1056 21 1051 6 998 22 1044 7 1056 23 1043 8 1056 24 1044 9 1031 25 1044 10 1053 26 1042 11 1054 27 1042 12 1054 28 1038 13 1058 29 807 14 1052 30 1021 15 1053 16 1055

S 0 UNIT SHUTOOWNS AND POWER REDUCTIONS 00CRET NO. 50 - 277 UNIT NAME PE ACH SOTTON UNIT 2 0 -- -- -------------

DATE DECEMBER 10, 1980 O REPORT MONTH NOVEM8ER, 1980 COMPLETED BY PHILaOELPHI A ELECTRIC COMPANY W.M.ALDEN O

ENGINEER-IN-CHARGE

. NUCLEAR SECTION GENERATION DIVISION-NUCLEAR 3 TELEPHONE (2158 841-5022 D l l l l l METH00 0F l LICENSEE 15YSTENICONPONENTI CAUSE AND CORRECTIVE l (TYPE 100RATIONIREA50N15 HUTTING 00WNI EVENT l CODE I CODE I ACTION 10 No.1 OATE I (111 (H004511 (2) l REACTOR (3) l REPORT f l (4) l (5) l PREVENT RECURRENCE I 1 i  ! l . I i 1 1 30 l 801105 l F l 012.6 l A l 1 1 NA l HA l VALVEX l ELECTRO-HYORAULIC CONTROL LEAR ON fl 3 1 l 1 l l l l l l CONTROL VALVE I l l l l l 1 1 1 33 l 801114 I F l 048.3 l A l 3 I NA I 50 l VALVEX l FEE 0 WATER LE AK AT HIGH PRES 5URE COOL ANT

[] l l 1 l l l l l l INJECTION TESTABLE CHECA VALVE I i i I I i 1 l l .

R$ $ 801117 l F i 026.4 i A I 3 l NA l IA I INSTRU l APRM HI-FLOX AUTOMATIC SCRAM 00E TD '2A' D I l t l l l l l l R.1 CIRC. FLOW CONTROL SYSTEN FAILURE I l 1 1 I I I I i 15 1 801122 1 5 1 000.0 i H l 4 l NA I RC l ZZZZZZ l LL A0 DROP FOR CONTROL A00 SEQUENCE EXCHANGE C) l I I I i 1 I I I I I I e7.3 I I I I i l i til (2) (33 (4)

F - FORCEO REASON METHOD EXHIBIT G - INSTRUCTIONS l 5 - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF OATA l

8 - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE P C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER) i 0 - REGULATORY RESTRICTION 4 - DTHER (EXPLAIN) FILE (NUREG-01613 b E - OPERATOR TRAINING + LICENSE EXAMINATION

" - ADMINISTRATIVE ($1

, - OPERATIDNAL ERROR (EXPLAIN) h H - OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE y

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PE ACH BOTTOM UNIT 3

DATE DECEMSER 10 1980 REPDRT NONTH NOVEMSER, 1980 COMPLETED SY PHILADELPHIA ELECTRIC COMPANY

$ W.M.ALDEN

ENGINE E R-IN-C HAR GE NUCLEAR SECTIDN b GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022

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' l ITYPElDURATIDNIRE ASONISHUTTING OOWNI l METHOD OF l LICENSEE 15YSTEMICDNPONENTI CAUSE AND CORRECTIVE EVENT 4 CODE i CODE l ACTIDN 10 3 NO.1_ DATE

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_ _ _ (23 I REACTOR 431 1 REPDRT e 1 (48 l (5) l PREVENT RECURRENCE 1 1 I l i I i l 19 1 801129 l 5 l 000.0 i H l 4 1 NA 1

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F - FORCED REASDN METHDD EXHISIT G - INSTRUCT!DNS 5 - SCHEDULED A - EQUIPMENT F AILURE (EXPL AIN) e 1 - NANUAL FDR PREPARATIDN OF DATA 8 - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

C - REFUELING ENTRY SHEETS FDR LICENSEE

' 3 - AUTDMATIC SCRAM. EVENT REPORT (LERI 0 - REGULATORY RESTRICTION 4 - DTHER (EXPLAIN)

E - OPERATDR TRAINING + LICENSE EXAMINATION FILE INUREG-0161)

F - ADMINJ5YRATIVE (5) p G - OPERATIONAL ERROR (EXPLAINI H - OTHER(EtPLAINI d

EXHIBIT I - SAME SOURCE i

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UPtROlihG DASO MtPUM8 DOCKET No. 50 - 277 DATE DECEM8ER 10, 1980 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M. A L DE N ENGINEER-IN-CHAAGE NUCLEAR SECTIDN GENERATIDN DIV!530N-NUCLEAR TELEPHONE (215) 641-5022

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OPERATING STATUS

1. UNIT NAME: PEACH SOTTOM UNIT 2 1 NOTES: THIS UNIT EXPERIENCED l 1 I

2. REPORTING PERIOD: NOVEM8ER, 1980 1 THREE MAJOR QUTAGES AND I l  ;

3. LICENSED THERMAL POWER (MWTis 3293 I ONE MAJOR POWER REDUCTION l l 1 4 NAMEPLATE R ATING (GROSS MWEl a 1152 l 1 1 I

5. DESIGN ELECTRICAL RATING (NET MWEl s 1065 1 1 1 i

6. MAXIMUM DEPENDA4LE CAPACITY (GROSS MWEl f 1098 l l l . I

7. MAXIMUM DEPENDA8LE CAPACITY (NET MWEls 1051 l l

8. IF CHANGES OCCUR IN CAPACITY RATING 7 (ITEMS NUWdER 3 THRDUGH 71 SINCE LAST REPORT, GIVE RE ASONS:

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWEls

10. REASONS FOR RESTRICTIDMS, IF ANYI THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD T20 4,040 56,184

12. NUMBER OF HOURS RE ACTOR WAS CRITICAL 669.9 4,09 3.3 41,848.7

13. RE ACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.3 14 Houas GENERATOR ON-LINE 632.7 3,839 0 40,821.8

15. UNIT RESERVE 5NUTDOWN HOURS 0.0 0.0 0.0 l 16. GROSS THERMAL ENERGY GENERATED (MWHi 1,935,647 11,457,326 118,222,970 1

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 649,400 3,815,220 38,873,450

18. NET ELECTRICAL ENERGY GENERATED (MWHI 623,838 3,632,242 37,248,027

19. UNIT SERVICE FACTOR 87.9 47.7 72.7

20. UNIT AVAILA8ILITY FACT 0a 87.9 47.7 72.7

21. UNIT CAPACITY FACTOR (USING MDC NET) 82.4 43.0 63.1

22. UNIT CAPACITY FACTOR (USING DER NET) 81.4 42.4 62.3

23. UNIT FORCED OUTAGE RATE 12.1 3.6 6.1 24 SnuTDOWNS SCHEDULED OVER NEXT 4 MONTHS (TYPE, DATE, AND DURATIDN OF E ACHi s

25. IF 5HUTDOWN AT END OF REPORT PERIDO, ESTIMATED DATE OF STARTUP

26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATIOMI: PDRECAST ACHIE VE D INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

. H P t R 41 [ N(, D A l a P f Prp t DOCKET NO. 50 - 278 OATE DECEM8ER 10, 1980 COMPLETED BY PHILADELPHI A ELECTRIC COMFANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLE AR TELEPHONE (215) 841-5022 OPERATTNG STATUS

1. UNIT N AME PE ACH BOTTOM UNIT 3 l NOTEst THIS UNIT EXPERIENCED NO l

-_. l l

2. REPORTING PERIDOS NOVEMBER, 1980 l MAJOR DUTAGES AND ONE I I l

3. LICENSED THERMAL POWERIMWTis 3293 l MAJOR POWER

• REDUCTION I I l 4 NAMEPLATE RATING (GROS 5 MWEla 1152 l l

...  ;

l S. DESIGN ELECTRICAL RATING INET MWEls 1065 I I

1 1

6. MAXIMUM DEPENDA8LE CAPACITY (GROS $ MWEls 1098 l l l 1

7. MAXIMUM DEPENDA8LE CAPACITY INET MWE l s 1035 l 1

8. IF CHANGES DCCUR IN CAP ACITY RATINGS IITEMS NUMSER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY INET MWEls

10. REASDNS FOR RESTRICTIONS, IF ANY:

THIS MONTH VR-TO-0 ATE CUMULATIVE

11. HDURS IN RE PORTING PERIOD 720 8,D40 52,080

12. NUMBER OF HOURS RE ACTOR WAS CRITICAL .720.0 6,e64.4 41,512.5

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 14 HOUR S GENE R ATOR OM-LINE 720.0 6,461.8 40,393 6 IS. UNIT RESERVE SHUTDOWN HOUR $ 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 2,320 694 20,592,130 114,811,284 l

17. GROSS ELECTRIC AL ENERGY GENERATED IMWHI 771,490 6,837,400 37,423,260

18. NET ELECTRICAL ENERGY GENERATED (MWM) 742,603 6,581,544 35,926,384

( 19 UNIT SERVICE FACTOR 100.0 80.4 77.6 l

i 20. UNIT AVAILA8ILITY FACTDR 100.0 80.4 77.6 1

21. UNIT C APACITY FACTOR (USING MOC NET) 99.7 79.1 66.7

22. UNIT CAPACITY FACTOR (USING DER NET) 96.8 .76.9 64.8

23. UNIT FDRCED OUT AGE RATE 0.0 10.5 7.4

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND OURATION OF EACHis REFUELING / MAINTENANCE, 3/7/81, SIXTEEN WEEKS

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTup

26. UNIT S IN TEST STATUS (PRIDR TO COMMERCI AL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATIOM -

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locact 240. >u-ar, Attachment to Monthly Operating Report hr November 1080 REFUEING INFORMATION s

1. Name of facility:

Peach Bottonit! nit 2

2. Scheduled date for nort rettioling shutdown:

January 2, 1982 l 3 Scheduled date for restart following reftaeling:

\ .

F6bruary 13, 1982 L

[ 14 Will refueling or resumption of operation thereafter require a

+=ah=iaal specification change or other 11a==== aumandment? ,

Yes.

If answer is yes, what,'in general, will there be?

Toohnical Specifications to sooommodate reload fusel.

Modifloations to reactor oore operating limits are earpooted.

5 Sobeduled date(s) for submitting proposed licanning action and

%gting information:

November 13, 1981

6. I + gt t licensing ocasiderations assooisted with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant abanges in feel design, new operating procedures Bone earpooted.

l  !

7 TM number of fuel asamblies (a) in the oore and (b) in the spent  ;

Jesi storman pools (a) core - 7614 Fuel Assemblies (b) Fuel Pool - 910 Ftaal Assemblies -

l 8. The present 14a==w spent ftsel pool storage espeoity and the size l cf any increase la licensed storage espacity that has been requested

or is p1mem*4, in number of final assemblies

The spent ftaal pool eterego capacity has been relicensed for 2816 final assemblies.

9 The projected date of tt.e last refueling that een be disaharged to the opent ftsel pool assuming the present liosamed empemity.

• 'T' September,1990 D""Dr B

,ccJ c .W.. .3

JA>cks t, No. S0-2IO

, Attachment to Monthly Operating Report For November 1980 1

1

1. Mene of facility:

Peach Bottom thit 3 1

2. aah'ad date for next renseling shutdown: l Merah 7, 1961 3 helad date for restart following refueling:

June 27, 1961

4. Will refueling or resumption of operstioa. thereafter require a technical specification oberge or other license assedmont?

Yes. .

If onewer le yes, idiate in general, will Abese be?

i Technical specification oheness to " to reload fuel.

Modifloations to remotcc oore operating limits are expooted.

5 aa u 'ad date(s) for euhaitting proposed 'ia===iar eation and supporting information:

Marsh 6, 1961

6. Importent 14--i=- ==1 Ammtions assoSisted With refMeling, e.g. ,

new or different fuel decian or supplier, imurerieved design or performarm emelysis methode, eipitioent ebensee in feel design, new operating procedures:

None expected.

7 Tae mmber of fuel seassblies (a) in the oore and (b) in the = pent fuel stores pools (a) cor. - 76k Fuel Assemblies (b) Puel Fool - 712 Irradiated Fuel assemblies l 8. h present 11a===ad opent fuel pool etereas esposity and the eiso of any inorsees in lia===ad stozuge omstoity that has been requesi,e.1 or is planned, in number of fuel meesmblies:

N spent fuel pool storess aspeoity hoe been relioensed for 2816 Aaal eseeablies.

9 The projected date of the lost refueling ht een be Atenhap to the opent fuel pool assumir4r the present lia==ad ospesity:

September,1991

PEACH BOTTOM ATOMIC POWER STATION NARRATIVE

SUMMARY

OF OPEHATING EXPERIENCES NOVEMBER 1980  ;

UNIT 2 OPER ATI0ilS On November 1, adjustments to the jet compressor steam pressure caused a brief load reduction to 67% due to a decrease in condenser vacuum. Between November 2 and November 3, load was reduced 100 MWe for approximately four hours due to river temperatures difference. On November 5, the unit was removed from service to correct an EHC oil leak on #4 turbine control valve. Coincident with the EHC oil leak HPCI was declared inoperable for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to correct a failed resistor in its EGM ricvcenor. The unit was returned to service on November 6. On November 14, the unit was removed from service due to a HPCI testable check valve leak. During reactor shutdown a low steam pressure scram occurred due to the mode switch not being taken out of "RUN". The unit was returned to service on November 16. Failure of a recirculation pump speed controller caused a high APRM flux scram the next day. The unit was returned to service on November 18 and reached full power on November 21. Load was reduced between November 22 & 23 to accommodate a control rod pattern adjustment.

UNIT 3 OPERATIONS Power recovery from the late October outage was completed by November 2, when the A-1 water box was removed from service due to tube leaks. On November 3, a load reduction of 150 MWe was necessary to accommodate a control rod pattern adjustment. On November 6, power was reduced to approximately 560 MWe due to a brief loss of the 'B' recirculation pump caused by the failure of a reactor level switch. On November 23, it was necessary to l manually isolate the reactor' water clean-up system because of a minor pipe leak between the inlet isolation valves. Repairs are in progress. Between November 29 & 30, a power reduction was taken to adjust the control rod pattern.

l i

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