ML20126B681

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Monthly Operating Repts for Feb 1980
ML20126B681
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/10/1980
From: Alden W
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20126B678 List:
References
NUDOCS 8003180409
Download: ML20126B681 (9)
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AVERAGE DAILY UN11-OWER LEVEL COCKET NO. 50 - 277 UNIT PEACM BOTTOM UNIT 2 DATE MARCH 10 1980 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALOEN E NG IN E E R-IN-CH AR GE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) P41-5022 MONTH FEBRUARY 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DALLY PuwER LEVEL (MWE-NET)

(MWE-NEl) 1 990 17 974 2

791 18 940 3

798 19 963 4

792 20 959 5

786 21 954 6

786 22 957 j

7 743 23 966 8

160 24 962 9

788 25 957 10 872 26 952 11 1015 27 949 12 994 28 946 13 990 29 942 14 964 15 960 l-16 975 i

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a 00CKk 1 NO. 50 - 277 DA TE MARCH 10 1980 COMPLETED BY PHILADELPHIA FLFCTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SEC110N GENERAT ION 01.V1510N.NUCLk AR TELEPHONE (215) 841-5022 OPERATING STATUS

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1. UNIT NAME: PE ACH BOTTOM UN11 2 1 NOTES: TH15 UNIT EXPERIENCED I

l l

2. REPORTING PERIOD: FEBRUARY, 1980 l

ONE OUTAGE AND ONE l

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3. LICENSED THERMAL POWER (MWT):

3293 i

POWER REDUCTION.

l l

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4. NAMEPLATE RATING (GROSS MWE):

1152 l

1 l

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- _ _. ~.. - -

5. OE51GN ELECTRICAL RATING (NET MWE ls 1065 l

1 l

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6. M AXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098 l

l g

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7. MAX 1 MUM DEPENDABLE CAPACITY (NET MWE):

1051 l

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8. IF CHANGES OCCUR IN CAPAC11Y RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPOR1, GIVE REASON 5:

9.

POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)*

10. REASONS FOR RESTRICTIONS, IF ANY THIS MONTH YR TO-DATE COMULA11VE
11. HOURS IN REPORTING PERIOD 696 1,440 49,584
12. NUMBER OF HOURS RE ACTOR WAS CRITICAL 696 1,043 38,798
13. RE ACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 690.2 1,004.2 37.987.0
15. UNIT RESERVE SHUTDOWN HOUR 5 0.0 0.0 0.0 i
16. GROSS THERMAL ENERGY GENERATED (MWH) 1,951,289 2,782,416 109,548,060
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 642,440 911,120 35,969,350
18. NET ELECTRICAL ENERGY GENERATED (MWH) 621,293 875,740 34,491',525
19. UNIT SERVICE FACTOR 99.2 69.7 16.6 i
20. UNIT AVAILABILITY FACTOR 99.2 69.7 76.6 1
21. UNIT CAPACITY FACTOR (USING MDC NET) 84.9 57.9 66.2
22. UNIT CAPACITY FACTOR (USING DER NET) 83.8 57.1 65.3
23. UNIT FORCED OUT AGE RATE 0.0 1.2 6.2
24. SHUTDOWN 5 SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND OURATION OF EACH):

REFUELING, 3/21/80 THIRTEEN WEEKS.

25. IF $HUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP
26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

UNIT ShtTLOWN5 AND PCwEk kiDUCTIONS DOCKET NL. SG - 277 UNIT NAME PE ACh 20lIOM bNIT 2 DATE MAR (M 10 1960 REPOkT MONTH FE6kUARY, 19ED COMPLETED BY PHILADELPHIA EEECTkl0 COMPANY W.M.ALDEN ENGINEEk-IN-CHARGE NUCLEAR SECTION GENERATION OIVISION-NUCLEAR TELEPHONE (2153 841-5022 1

I I

I l METHOD OF 1 LICENSEE 15YSTEMICOMPONENTI CAUSE AND CORRECTIVE I

ITYPEIDURATIONIREASONISHUTTING 00WN1 EVENT l CODE l CODE I ACTION TO NO.I DATE I (Ill (HOUR 5ll (21 l kEACTOR 131 l REPORT e i 143 l (5) l PREVENT RECURRENCE I

I I

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5 1 600201 1 5 1 0.0 l

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N ONE i

HA I VALVEX l al TURBINE STOP VALVE TEST.

IT FAILED I

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l l TO REOPEN.

POWER REDUCED 10 751.

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I 6 I 600201 1 51 5.8 l

B l-1 I

NONE I HA I VALVEX l el TURBINE STOP VALVE REPAIR.

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I T I 800209 I 5 I o.o i n i 4

i NDNE I RC l ZZZZZZ l LOAD DROP FOR CONTROL ROD ADJUSTMENT.

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5.8 l

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ill (2)

(3)

(4)

F - FORCED REASDN METh00 EXHIBIT G - INSTRUCTIONS 5 - SCHECULED A-EQUIPMENT FAILURS (EXPLAIN) 1 - MANUAC F OR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCR AM.

ENTRY 5HEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LERI D - REGULATORY RESTRICTION 4 - DTHER (EXPLAINI FILE (NUREG-Ol61)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (55 G - GPERATIQNAL ERROR (EXPLAINI H - OTHEktExPLAINI ExHlEli 1 - SANE SUURCE k

AVERAGE DAILY UNIT FOWEk LEVEL 00CKET NO. 50 - 2.76 UNIT PEACH BOTTUM UNIT 3 DATE MARCH 10 1960 COMPANY PHILA0ELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 641-5022 MONTH FEBRUARY 1980 OAY AVERAGE OAILY POWER LEVEL OAY AVERAGE OAILY POWER LEVEL (MWE-NET)

(MWE-NE1) i 1

0 17 1076 2

0 18 1077 3

0 19 1073 4

0 20 1073 5

0 21 1075 6

163 22 1076 7

908 23 1061 8

986 24 1076 0

640 25 1060 10 1064 26 1060 11 1060 27 1079 12 1061 26 1061 13 1082 29 1060 14 1070 15 1076 16 1074

OPERA 11NG'OATA REPO4I 00CKE1 NO. to - 276 OATE MAkCH 10 1060 COMPLETED BY PHILADELPHIA ELECTMlC L(PvANY W.M.ALDEN E NG I N E E R -I N-C Ha k b E NUCLEAk SECTION GENERATION 01V153LN-NOCLtaa I E L E PHON t (215) 641-5022 OPEEAllNO LTATUS

3. UNIT NAME s PE ACH BOTTOM UNIT 3 l NUTh$s THIS UNIT EXPERIENCE 0 UNt i

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2. R E P0411 NG P E R 100 3 FEBkUARY, 1980 1

OUTAGE AND ONE MAJ0k POWik i

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3. LICENSED THERMAL POWERIMWils 3293 l

RE O UG T ION.

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NAMEPLATE RATING (GkO55 MWEls 11b2 l

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5. DE SIGN E LECTRIC AL RAT ING INkT MWE l s 1065 l

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MAXIMUM DEPE NOA6L E CAP ACITY (GROSS MWEls 1098 l

1 l

7. MAXIMUM DEPENDABLE CAPACITY INET MWhl:

1035 l

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IF CHANCES DCCUR IN C APACITY RATINGS (11EM5 h9MBER 3 THkOUGH 71 SINCE L AST RE PQkT, LIVE me A buNhl 9 P0 wE R LEVEL TO WHICH RESTRIC1E0e IF ANY (NET MWEls

10. REA5ONS FOR RESTRICTIONS. IF ANY:

THIS MONTH YR-TO-DATE CUMUL ATivt

11. HOUR 5 IN REPORTING PERIOD 696 1,440 45.4e6
12. NUMBER OF HOUR 5 RE AC70R WA5 CRITICAL

$44 1,153 sb,44u l). REAC10R 6F5ERVE SHU100WN HOUR 5 0.0 0.0 0.0 14 HOUR 5 GENER ATOR ON-LINE 561.1 1,101.6 3 f 033.t

15. UNIT RESERVE SHUT 00WN HOURS 0.0 0.0 0.0
14. GROSS THERMAL ENERGY GENERATED (MWHI 1,796,642 3.502,918 97.722.072 I T. GR055 ELECTRIC AL ENERGY GENE RATED (MWH) 604.670 1,178,730 31,7t4,t40

'8.

NE T ELECTRICAL ENERGY GENERATED (MWH)

$86,4b2 1,139.911 30,4e4.711 10 UNIT SERVICE F ACTOR 80.6 76.5 17.0

20. UNIT AVAIL ABILITY F AC TOR 80.6 76.5 77.0
21. UN IT C A P AC I T Y FACTOR (USING MDC NEll 61.4 76.5 (4.h 1

it. UN11 C AP ACITY F ACTOR (USING DER Nhil 79 1 74.3 (2.4 4

23. UNIT FORCEO OUTAGE RATE 0.0 0.0 6.e 24 5 HUT 00WN5 $CHEDULEO DVER NEXT 6 MONTHS ( TYPE e DA TE, AND DUR A110N OF EAChas REFUELING, 3/7/81. ELEVEN wtEK5 2b. IF 5 HUT 00WN A T E ND OF RE POR T P E R I DO, ESTIMATE 0 DATE OF $TARTUPS
26. UN IT S IN 1 E 51 51A105 (PRIOR 10 COMME RCI AL OPER A110Nis FORECAST ACHIEVED INITIAL CRITICAL 11Y INITIAL ELECTRICITY COMMERCIAL OPERATION

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9 dNIT 5*uTCO.N5 aNC FCmEk REDUCTIONS DOCKET NO. 50 - 27e UNIT NAME PEACF BOTTOM ONil 3 CATE MARCH 10 Is?O kEPOR1 MONTH FEBRUARY, 1980 COMPLETED BY P LADELPhia ELECTk!C COMPANY W.M.ALDEN E NG INE E R-IN-C HA kGE NUCLEAR SECTION GENERAT ION 01V1510N-40CL E AR TELEPHONE (215) 841-5022 l

l 1

l l METHOD OF 1 LICE NSE E 15Y51EMICOMPONENil CAUSE AND CGRRECTIVE I

ITYPEIDURATIOklREASON15 HUTTING DCWN!

EVENT l CODE l CODE l

-ACTION TO NG.I DAIE l till (HOUR $ll (2) I sEACTOR (33 i RE POR T e 1 (4) l (5) l PREVENT RECORRE NCE I

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3 1 *00201 1 5 l 134.9 1

8 1 3

l NONE I Cb I PUMPXX l 3B REACTOR RECIRC. PUMP SEAL REPLAEEMENT.

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I 4 l *00209 I 51 0.0 i

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l NONE I kC l ZZZZZZ l LOAD DROP FOR CON 1h0L ROD ADJUSTMENT.

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l 134.9 I

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I (1)

(2)

(3)

(4)

F - FORCED REASON NETHOO EXHIBIT G - INSTRUCTIONS 5 - Sche DULE D A-EQUIPMENT FAILURE IEXPLAINI 1 - NANUAL FOR PREPARATION OF DATA 8 - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY SHEETS FDR LICENSEE C - REFUELIkG 3 - AUTDMA TIC SCRAM.

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAINI FILE INUREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE 151 G - OPERATIONAL ERROR (EXPLAINI H - OTHERIEXPLAIN)

EXHIBIT I - SAME SOURCE

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Docket No. 50-277 Attachment to Monthly Operating Roport for Februa ry,1980 REFUELTNG IhTORMATION 1.

Namo of facility:

Peach Dottom Unit 2 2.

Scheduled dato for next refueling chutdown:

March 21,1980 3

Schedulod dato for rectart following refueling:

June 21, 1900 h.- Will refueling or recumption of operation thoroafter require a technical specification chango or other licenso amendment?

Yes.

If answor ic yoc, what, in conoral, will thoco bo?

Technical specification changes to accommodate reload fuel.

Modifications to reactor core operating limits are expected.

5 Scheduled date(c) for cubmittinc proposed licensing action and cupporting infomation:

Submitted March 3, 1980 6.

Important licencinc considerations associated with refueling, o.g.,

new or differont fuel decicn or cupplior, unroviewed dosicn or performance analycic methode, significant changes in fuel decicn, new operating proceduros:

Initial' utilization of General Electric pro-proccurized Fuel Accomblioc for thic Unit.

7 Tho number of fuel accomblioc (a) in the coro and (b) in the cpont fuel storago pool.

(n) Coro 76h Fuel Accomblice (b) Puol pool 610 Irradiated Fuel Accomblico 8.

The presont licenced spent fuel pool storage capacity and the cizo i

of any increase in licenced storago capacity-that has boon requocted or io planned, in number of fuol assembliec:

Tho opent ruol pool ctorace capacity has been rolicenced for 2816 fuel accemblics.

[

9 The projected dato of the last refueling that can be dischargod to tho epont fuel pool accuming the procent licenced capacity:

Goptembor, 1990 l

lo.me t wo. '50-27,8 A L Litchmen L to Mon Lhly Operating Repo,rt For Februaty, i t)UO T(MM11&li!G ImiiMN1'[00

1. Nemo of facill Ly:

Poach llottom Unit 3

2. Scheduled dato for f. ext refuelinc chutdown:

-Msrch 7, 1981

3. Scheduled dato for rect:trt followinc refuelinc:

May 23, 1981

h. WJll refueling or renunplion of operal. ion thereafluc requirc a technical specification chanco or other licenco nmendment?

Ycs.

If ancwor ic yac, what, in gonoral, will thoco bo?

Technical specification changoc to accomodato roload fuel.

Modifications to roactor coro oporating limits aro expected.

5. Scheduled dato (c) for submitting propocod licensing action and j

supporting infonnation:

January 23, 1981.

6. Important licencing concidorations accociated with refueling, e.g.,

now or different fuel decicn or supplier, unroviewed deciCn or perfonwinco analycic methode, clenifictinL chancon in ruol docien, now oporating procedureus Nonc cxpected.

7. The number of fuel acco'ablice (a) in the coro and (b) in the cpont fucl cLoraco pool:

a)Coro-76hPuolAcucmblice b) Fuol pool

'!12 Irradiated Fuel Accomblice

8. Tho procent licenced upont fuel pool ctoraco capacity and the sizo of any incroaco in licencod storaco capacity that,han been requocted or in plannod, in number of fuel accomblicc:

The opent fuel pool atoraco capacity hac bocn rolicenced for 2016 fuel accomblioc.

9. The pro,iceLod daLo of Lhe lacL ccfuoiinc I,haL c:ui bo diucharged to Lho upont fuel pool acewning tho procent ilconced capacity:

Sep tembor, 1991, i

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s PEACH BOTTOM ATOMZd POWER STATION-p NARRATIVE

SUMMARY

OF OPERATING EXPERIENCES FEBRUARY, 1980 UNIT _2 Unit output was ' reduced to approximately 800 MWe from February 1 to February 7, due to. turbine stop valve not opening following routine testing. The turbine generator was removed from service on February 8 for approximately six hours to effect repairs.

The Unit was returned to maximum coastdown capacity of. 967 on February 11 following an adjustment to the control rod pattern during the power escalation.

On February 7 a HPCI and RCIC initiation and injection occurred as a result of an electrical transient to their controller power caused during transfer of loads on the computer MG set from its AC drive to its DC drive. Both systems were secured within one minute as a result of determining that their initiation was not warranted. On February 18, a load reduction of approximately 110 NWe was necessary for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> due to river temperature differential.

The Unit was returned to maximum coastdown capacity on February 19.

UNIT 3 The Unit was removed from service on January 29 in orde'r to

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replace the 3B recirculation pump seal. Tube leaks on the 2B and 2C feedwater heaters were also repaired.

Restart of the Unit was delayed until February 6 due to reactor water chemistry and to accommodate drywell entry for seismic inspection of some instrument lines. The Unit reached approximately 1000 MWe on February 7 and experienced a load reduction to about 900 MWe as a result of a run back of the recirculation pumps and the turbine - generator caused by a reactor level transient associated with testing the 'B' reactor pump.

The Unit was returned to rated power on February 10 following an interruption in power escalation to adjust the control rod pa t te rn.

. KEE/kif 3/10/80

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