ML19341A058

Monthly Operating Repts for Dec 1980

ML19341A058
Person / Time
Site:	Peach Bottom
Issue date:	01/10/1981
From:	Alden W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML19341A055	List: ML19341A054 ML19341A058
References
NUDOCS 8101210528
Download: ML19341A058 (10)

Text

f~'; '. l (l AVE 4AGi nAILy UNII P0dE: LEVEL DOCKET NO. f0 - 277 UN I T PEACH PCTTC* UNIT 2 OATE JANUARY 10, 10o0 COMPANY PHILADELPHIA E LEC1R IC COMPANY w.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENER A T ION 01 VISION-NUCLE AR E

1ELEPHONE (215) 341-5022 MONTH DECE MBER 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET) (MWE-NET) 1 1064 17 1074 2 1066 18 1074 3 1064 19 1074 4 -

1C67 20 1075 5 1067 21 1076 e 1C66 22 1080 7 1047 23 1083 s 1021 24 1086 o 107? 25 1084 10 1073 26 1075 11 1076  ?? 400 L2 1072 28 505 l' 1075 29 0 14 1073 30 77 1 *, 1074 31 84% .

1 16 1074

~

l

810121062TI

~ ~

,' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 278 UNIT PE ACH BOT TOM LNIT 3 DATE JANUARY 10, 1980 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 .

MONTH DE CE MB ER 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LE VE L (MWE-NET) (MWE-NET) 1 1056 17 8 93 2 1056 18 0 3 1059 19 0 4 -

1059 20 0 5 1058 21 0 6 1059 22 173 7 1047 23 938 6 1044 24 1040 l

9 1058 25 1019 10 1059 26 1024 i

11 1058 27 986 12 1057 28 1073 l

l 13 1057 29 1066 14 1059 30 1063 15 1056 31 1066 16 1055 e

OPERATING DATA Ri?ORI DOCKET NO. 50 - 277 OATE JANUARY 10, 1960 COMPLETED BY PHILADFLPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCL E A R SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (2151 841-5022 OPERATING ST ATUS

1. UNIT NA ME PEACH BOTTOM UNIT 2 l NOTES: THIS UNIT EXPERIENCED l I l

2. REPORTING PE RIOD: DECEMBER, 1980 l THREE MAJOR OUTAGES AND l

.___.___ .__... ...__ l l

3. LICENSED THERMAL POWERIMwT): 3293 l ONE MAJOR POWER REDUCTION l

___..__.....____ l l 4 NAMEPLATE RATING (GROS 5 MWE): 1152 l l .

l l S. DESIGN ELECTRIC AL RATING INE T MWEle 1065 l l l l

6. Max! MUM DEPENDA8LE CAPACITY (GROS 5 MwEla 1098 l l J l

7. M AXIMUM DEPENDABLE C APACITY INET MwEls 1051 l l

8. IF CHANGES CCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) $1NCE L A ST REPORT, GIVE RE ASO

9. POWER L EVEL TO WHICH R ESTR ICTED, IF ANY (NET MwEls

! 10. RE ASONS FOR RESTRICTIONS, IF ANY i

THIS MONTH YR.TD-CATE CUMULATIVE

~

11. HOURS IN REPORTING PERIOD 744 8,734 56,928

12. NUMBER OF HOUR $ REACTOS was CRITICAL 703.8 4,797 1 42,552.5

13. R E ACTOR RESE RVE SHUTDOWN HOUR S 0.0 0.0 0.0

==

14 HOURS GENEaATOR ON-LINE 691.0 4,530.0 41,512.3

15. UNIT RESERVE SHUTOOWN HOURS 0.0 0.0 0.0

16. GROSS T HERMAL ENE RGY GENER AT ED IMwM) 2,198,102 13,655,428 120,421,072

17. GROSS E LECTRICAL ENERGY GENERA TED (MwH) 739,650 4,554,870 39,613,100

18. NET ELECTRICAL ENERGY GENERATED (MwHI 711,637 4,343,879 37,959,664

19. UNIT SERVICE FACTOR 92.9 51.6 72.9

20. UNIT AVAILABILITY FACTOR 92.9 51.6 72.9

21. UNIT CAPACITY FACTOR (USING MOC NET) 91.0 47.1 63.4

22. UNIT CAPACITY FACTOR tuSING DER NET) 89.8 46.4 62.6

23. UNIT FORCEO CUTAGE RATE 5.9 4.0 6 .1 24 SHuf 00wNS SCHEDULED OVER NEXT 6 MONTHS ITYPE, DA TE AND OURA TION OF EACHlt i

25. IF SHUTOOwN AT END OF REPORT PERIOD, ESTIMATED OATE OF STARTUPS

26. UNITS IN TEST STA TUS (PRIOR TO COMMERCIAL OPERATIONlt FORECAST ACHIEVED l

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

ODERATING DATA RED 007 DOCKET NO. 50 - 278 DATE JA NU ARY 10, 1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY w.M.ALGEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (2151 841 5022 DPERA TING ST A1US

1. UN I T N A ME : PEACH BOTTOM UNIT 3 l NOTES: THIS UNIT EXPERIENCED ONE l l l

2. RE POR TING PE RIODI DECEMBER, 1980 l MAJOR OUTAGE AND ONE l

=. .. ..._.

l l

3. L ICENSE D THERHAL P0wER(MWT ): 3293 i MAJOR POWER REDUCTION l l

4 N AMEPL A TE R ATING (GROSS MwEl

• 1152 l 1 -

l l

5. DESIGN ELECTRICAL RATING (NET wwElt 1065 l l

.._____.. l l

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MwE l s 1098 I l l l

7. MAAluuM DEPENDABLE CAPACITY (NET MWEls 1035 l l S. IF CHANGE S OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 73 SINCE LA ST REPOR T, GIVE RE ASi

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

10. REASONS FOR RESTRICTIONS. IF ANY THIS MONTH YR.TO-DATE CUMULATIVE

11. HOURS IN REP 0aTING DE21DD 744 8,784 52.824

12. NUMBE R OF HOURS REACTOR WAS CRITICAL 649.7 7.316.1 42,162.2

13. RE ACTOR RESE RVE SHUTDOWN HOURS 0.0 0.0 0 .0 14 HOUR S GENER A TOR ON-LINE 631.2 7,093.0 41,074.8

15. UNIT RE SERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS TbERMAL ENERGY GENERATED (MWH1 2,031,665 22.623,795 116,842.949

17. GaOSS E LECTRICAL ENERGY GENERATED (MWHI 678,730 7,516.180 38,102,040

18. NE T E LECTRIC AL ENERGY GENE RA TED (MWHI 652,259 7,233,843 36,578.663 19 UNil SERVICE FACTOR 64.8 80.7 77.7

20. UNIT AVAILABILITY FACTOR 84.8 80.7 77.7

21. UNIT CA PACITY FAC10R (USING MDC NET) 84 7 79.6 66.9

22. UNIT CA PACITY FACTOR (USING DER NET) 82.3 77.3 65.0

23. UNIT FORCED OUTAGE RATE 15.2 11.0 7.6  !

24. SHUT 00dNS SCHEDULED OVER NEXT 6 MONTHS ( TYPE , DA TE AND DURA TION OF E ACH 13 aEFUELING/ MAINTENANCE, 3/7/81 TWENTYTHREE WEEKS

25. IF SHUT 00hN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPt

26. UNITS IN TEST STA TUS (PRIOR TO COMMERCIAL OPERATIONi t FORE CA ST ACHIEVED INITIAL CRITICALITY l

INITIAL ELECTRICITY COMMERCIAL OPERATION

i UNIT $HUTDOWNS AND POWER REDUCTIONS DOCK ET NO. 50 - 277

.= - --

UNIT NAME PEACH POT 10M UNIT 2 DATE JANUARY 10, 1980 REPORT MONTH DECE"BER, 1980 COMPLETED BY PHILADELPHIA EL ECTR IC COMPANY

_= . = = . -

W.M.ALDEN E NG INE E R - IN-C H A RG E NUCLEAR SECTION GENER AiION 01VI SION-NUCLE AR TELEPHONE (2153 841-5022

=

l l l l l METHOD bF 1 LICENSEE 15YSTENICOMPONEbilCAUSE A ND CORRE CT IVE I ITYPElDURATIONIREA50N15 HUTTING DOWN1 E VE N T l CODE l C OD E I #CTION 10 NO.I DATE I till (HOURSil 121 1 REACTOR 133 l R E POR T 5 l (4) l (5) l PRE VENT RECURRENCE I i l l I i 1 I i 16 l 801226 l F l 000.0 l A 1 4 l NA l NF 1 CKIRR K l LOAD DROP OUE 10 LOS$ OF 2B C 2C CIRCULATING I I l l l l l l l WATER PUMP 5 CAUSED BY CIPCUI T BREAKER TRIP l l l l 1 I I I I ON 2G4-PA BUS.

1 I I I l l I I. I 17 l 801227 I 5 1 010.0 l A i 1 1 NA l HA l VALVEN 1 EHC OIL LEAKS ON W1 AND #2 IURBINE l l l l l l l l l CONTROL VALVES.

1 I I I I I l i I 18 I 801228 i F I 040.7 1 A 1 3 i NA l CC l V AL VE X l SCRAM DUE TO TURBINE TRIP FROM HIGH tEVEL l l l l l l l l l IN 'D' MOISTU*E SEPARATOR DRAIN TANK.

I I I I i i i I I 19 1 801230 1 F l 002.3 l A l 1 1 NA l HH l XttuxX l INSUFF ICIENT CONDENSER V AC UUM 00E TO OUTAGE l 1 l l l l l l l OF 2e C 20 CIRCUL A TING W AT ER DUMPS FOR I I l l l l 1 l l PREANER CALIPRATION.

l l 1 ----- 1 I l l l l l l l 53.0 1 1 l l l 'l i

til (2) (3) lab

• - 500CEO REASON METHOD EXHIBli G - INSTRUCTIONS 1 - SLhEDULEO A - E OUIP"ENT FA LuoE (EXPLAIN) 1 - MANttAL FOR PREPARATION OF D4f8 8 - MAINTENANCE OR TEST 2 **NUAL SCPA*. ENTRY 5HEETS FCR L IC EN 5E E C - REFUELING 3 - AUTowATIC SCRAM. EVENT REPORT *LERS O - REGULATORY RESTRICTION ' - OTHER (EXPLAINI FILE I NUo E G-0161 )

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE 15)

G - OPE R AT IONAL ERROR (EXPLAINI H - OTHERIEXPLAINI E*H191T I - SAPE S OURC E

UNIT SHUT DCwNS AND POWTP REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEarH ROTTOM UNIT 3 DATE JANUARY 10, 1980 REPORT MONTH DECEMBER. 19EO COMPLETED BY P LADELPHIA EL EC TR IC COMP ANY W.M.ALDEN ENGINEER-IN-CHARGE -

NUCLEAR SECTION GENERATION DI VI SI DN-NUCL E AR TELEPHONE 12151 841-5C22 l l l l l MFTH00 0F l LICENSEE ISYS1E ulCCPPCNENil C AUSE AND CORREC T IVE I ITYPEIDUHATIONlREASONISHUTTING DowN1 EVENT l CODE l CODE I ACTION TO NO.1 DATE I (Ill (H00RSil (25 i REACTOR 43) l RIPORT

• 1 14) 1 (51 1 PRE VFNT R EC URRENCE I i 1 1 1 1 1 I I 26 l 801217 l F 1 112.8 i A l  ? l NA l CH I XXXXXX l SCRAM DUE TO REACTOR FEED PUMP TRIP CAUSED 1 l l l l l l l l BY PRESSURE TRANSIENT IN C ONDE NS AT E SYSTEM.

I 1 l l l l l l* I OUTAGE WAS E XTENDED TO REP AIR SCRAM 1 l l l l l l l l DISCHARGE VOLUME CONT!NUUUS WATER LEVEL 1 l l l l l 1 1 I MONITORING SYSTEM.

I I I i i i 1 I i

. 21 1 801227 l 5 1 000.0 1 H l 4 l NA l RC 1 ZZ2222 i LO AD DROP FOR ROD PATTERN ADJUSTMENT. '

i 1 1 ----- 1 1 1 l l l l l l 112.8 l l l l l l

. til (2) (3) (4)

F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S - SCHE DULED A - EQUIPMENT F AILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA P - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FDR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER) 0 - RFGULATORY RE STRICTION 4 - OTHER ( EX PL AIN) FILE INUREG-0161)

F - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE E51 G - OPERATIONAL ERROR (EXPLAIN)

H - OTHEnfEXPLAIN) EXHIBIT I - SAME SOURCE .

i

Docket No. 50-277 Att W _t to Monthly Operating Report For . December 1o80 REFUELING INFORMATION

1. Name of facility:

Peach Bottom Unit 2

2. Scheduled date for next refueling shutdown:

January 2, 1982

• 3 Scheduled date for restart following refueling:

February 13, 1982 1.4 Will refueling or resumption of operation thereafter require a technical specification char:ge or other license amendment?

Yes.

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

Technical Specifications to accommodate reload fuel.

Modifications to reactor core operating limits are expected.

5 scheduled date(s) for submitting proposed licensing action and supporting information:

November 13, 1981

6. Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

None expected.

7 The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

(a 4 (b} Core

) Fuel Pool- -761 Fuel 910 Fuel Assemblies Assemblies

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

The spent fuel pool stcrage capacity has been relicensed for 2816 fuel assemblies.

9 The projected date of the last refueling that can be discharged' to the spent fuel pool assuning the present licensed capacity.

September, 1990 l

- . mm m

, _ 9 9 9 cw c .\ .a ptACM 30TTo" AT0!!IC 90UER STATIO!'

NAMPATIVE

SUMMARY

OF OPERATING EXPCRIENOCS DECEMBER 1980 I!"IT _2 Opt?ATIOMT The unit operated at essentially full nower until a trin of the n

&C circulating water nunns occurred on neconher 26. The load was reduced to annroxinately 450 vue to recover vacunn until the feeder breaker for the associated nunn notor exciters could he recalibrated and reset and the circulatinc water punos restarted.

On necenher 27, load was reducad ae 6 a.n. to 325 "Uc to replace

.Recire. MG set brushes and to perforn a level response test on the scran discharce volume header as required by Supolement 4 -

tor 7C Bulletin 80-17. The unit was taken off the line at 6:33 p.n. on necenher 27, to repair E1C oil leaks on two control valves that could not he repaired with the unit on the line. The leaks were repaired and the unit was returned to service at 4:30 a.n. on Decenber 28.

At 19:16 n.n. on neconher 28, the unit scranned fron a no'isture separator drain tank high level turbine trip caused by problens with the associated dunn and drain valves. Difficulties with the NRC nandated scran discharge volume continuous monitoring systen delayed return of the unit until 3 p.n. on Decenher 30 It was necessary to again renove the unit from service to complete the recalibration of the B & C circulating water pump exciter breaker due to reduced condenser vacuun. "The unit went back on the line at 5:20 p.n. on December 30. The unit had achieved 8A percent power in the startup rann by the end of the nonth.

The following significant natntenance uork whs nerformed durina the nonth: On Deconher 3 qnd 4 the stand $v gas treatnent systen t rains were taken out of service one at a tine to renlace a heat detector. On 1econher 8 the E-4 diesel nenerator was blocked to reonir a leakins hellows on the enerlency service water outlet nining. The diesel nenorator was returned to service the sane shift. On necember 16 a 1/3" to a 3/16" nerforation was discovered in the energency service water pininn to the RCIC roon cooler. On December 25 the fire ounns au t oma t i ca lly started on LO header oressure when the undernround header cracked. The fire header was roontred and returned to nornal two days later.

UNIT _3 OPEnATIONS The unit onerated at essentially full oower until the unit scranned on low reactor water level on Deconher 17 due to a t rans ient in the condensate svsten which trinced two reactor f eed punns on low suction nressure. Insnoctions of some niant equionent and difficulties with the 50C nandated scran discharge volune continuous nonitoring systen delayed return of the unit until 1:15 p.n. on Decenher 22. On Decenher 27, a power reduction was taken to adjust the control rod pattern.

i l

o l

I

+ .

D** 3Y g

Page 2 N

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The followinc significant naintenance work uns nerforned durine the month:

On necenher 1 t h e '!PCI was nade inonerable for an insnection of "0-14, the t u r bi t .- S t e .1 n sunniv valve which had e xh i b i t e r! mone e lec t rical shnormalities. The valvo was fount! to he fully operable, and the 't " C I was returned to service on December 6.

The reactor water cleanu, systen onorated until neconher 14 with a temporary suction line while the nornal suction line was out of service for ninins. renlacement. On Decenber 14, the reactor water cleanun uns returned to service with a renaired .. u c t i o n ~

line, dunning to the condenacr.

On December 17 the 3B 9'S MC set tripned when the outnut b r e a '< e r onened. The voltage reoulator was replaced and the P.P S !'O set was returned to service.

h

Dockot No. 50-278 l

, Attachment to Monthly Operating Report  :

For Decenber 1980 l

REFUELING DDVRMATION

1. Name of facility l Peach Bottom Unit 3 j 2. Scheduled date for next reiheling shutdown:

l March 7, 1981 ,

3 Schedulod dato for restart following refueling:

August 1h, 1981

h. Vill refueling or resumption of operation thereafter require a technical specification change or other license a==ndment?

Yes.

If answer is yes,*what, in general, will ihese be?

Technical specification. changes to accommodate reload fuel.

Modifications to reactor core operating limits are expected.

5 Scheduled date(s) for submitting proposed licensing action and supporting information:

March 6, 1981

6. Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed desi6n or performance analysis methods, significant changes in fuel desi6 n, new operating procedures None expected.

7 The number of fuel assemblies (a) in the core and (b) in the spent fuel storage Pools a Core - 76h Fuel Assemblies b Fuel Pool - 712 W h ted Fuel Assemblies

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storsse capacity that has been requested or is planned, in number of fuel assemblies:

The opent fuel pool stora6e capacity has been relicensed for 2816 fuel assemblies. l 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Sentember. 1991

4 isP* % -

s  % & -

Mr. Joseph J. Gdovin promptly as practicable and that reasonable progress on the completion of such actions prior to restart is required in order to provide reasonable assurance that the facility can be operated safely over the long tena. The Commission's primary comitment is to a fair and thorough hearing and decision. Given this overriding imperative, it is the Commission's expectation that the Board will conduct the proceeding expeditiously. The decision on resumption of operation will be made by the Commission after the hearing is completed.

Sincerely, Cr::' :! - - :! .y

, !!. '.. . . . .a ,

Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

1. Ltr. of July 3,1980

2. Recent Report of the U.S. Department of Energy DISTRIBUTION Docket 50-320 NRC PDR LPDR Tera NSIC HRDenton EGCase PFine GZech/TJCarter TMI R/F BSnyder 100RBRMAL 1

n.c p NRR/TSB ,[NRR/TSB/C INRR/PPAS/D NRR/DD

. iNRRqIR ,[ i 5 "'*O .PFineypav i G.Zech. .  !.HLThompson EGCase

...HRC eton.. ,[ ,i ,

l ec r p 01/ /81 !01/ /81 01/ /81 01/ j

.,. .,. /81 .!.01/Il/81

,. .l 2: =:<u:a : 4: v:  :-:

OFFIC!A L R ECC R 2 CCi:'f w: +: -