ML18227B102

03/06/1975 Letter Operating Status Reports of February 1975

ML18227B102
Person / Time
Site:	Turkey Point
Issue date:	03/06/1975
From:	Schmidt A Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML18227B102 (16)

Text

~ 0 ~ ~

~ ~ ~

I )~

0 0 0

~

4 0 ~

~ ~ ~

g ~ 0 ~

~ ~ ~ ~

~ 0

~ ~

~ 0 III ~ ~ ~

I

~

I:

0

~

~

~ 0

~

~

~ 0 I

e

~

~ ~

~ ~

~ ~ ~ ~ ~-

~ ~

~ ~-

~

~

~ i ~ ~ 0 '

~ 0

~ ~ 0

~ ~ ~ ~

~ 0 I ~ ~ ~ I I '

0

~Vrcg5% ~ 0 ~ 0 j

~ ~ ~

~ ~ ' ~ ' 0 ~ 0 0 0

~ ~

0

~

~ a ~

0 ~ ) ~

~ ~ ~

0

~

) ~ 4

~ ~ g 0 ~

~ ~ e

~ ~

~ 0 ~

~

~

~ ~ ~ $ ~ ~

~ 0 0

~ ~ ~ ~

'I 0 ~

~

0

) ~ 0

~

~

~ 0 P ~

~ g

~

~ 0

~ 0 ~ ~

~ 4

~

~

' ~

0 l 0 4 0 ~

~ ~

(

~' C

'I

.O. SSX 0100 MIAMI,PLOIIIDA 03101

~y~l bg FLORIOA POWER 5 LIGHT COMPANY March 6, 1975 Office of Management Information and Program Controls U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

Attached are the February, 1975 Operating Status Reports for Turkey Point Unit Nos. 3 and 4.

Very truly yours, D. Schmidt Vice President VTC/cpc Attachment cc: Mr. Norman C. Moseley Jack R. Newman, Esquire 2672 HELPING BUILD FLORIDA

a, UN1T <<i~4~9:" "

Turkey Point U No. 3 REPORT MO" "'8, Februar, 1975 JD'I'Ii 4-

'arch ,, ~~~ ~5, ~1975~ ~ ~~ ~ M  % M4~% Vll1 4vlt CO~IVI.I:"fI!D I'Y V. T. Chilson TELEPI 10%1;; T~ 0 4%5'=623:1" Cx't. 2177'=

OPERATING STA'f US

1. Rk',PORTING PERIOD: 0001, 75 02 g.!ROUGI.!'4 00, 75 02 GROSS I IOURS IN IVI!70K!'lNG I'L'R10D: ~ 0 *

2. CURREN'fLY AUTIIORIZED'OWER LEVEL PIÃt) 2200 MAX. DEPEND. CAPACITY (IIHi'0 NET) 666

3. PONKR LEVEL 'IO Iy'IIICI-I RESTRICTED (IF ANY): (Mi7e NET) None

4. uEASQNS FQR RESfRICTIQNS (IF,ANY):

'11.1IS CUMiJ ITIVE IiSih% YR-'fO-DATE TO DATE

5. 1KJi!BLR OF HOURS TIK REACTOR WAS DT VTWAT C47Tt7 T&A7

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 668.0* 1 412.0 15 439. 7

6. REACTOR RESERVE SI.IUTDOWN HOURS ........ ' 7~ HOURS GENERA'IQR ON LINE ..., ~.... 665 2* 1 409 2 14 827.5 8.'NIT RESERVE SIIIJIDQNN I.IOURS .........., . 85.0

9. GROSS Tj-IERAL DIERGY "GENERA'fED9MI).... 1 404 960 2 995 121 25 675 145

10. GROSS ELECTRICAL ENERGY GENERATED p INH) o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 454 705 982 603 8 410 408 432 776 936 193 7 517 558

12. REACTOR AVAILABILI'I'YFACTOR +1 99.6 99.8 78.8

13. UNIT AVAILABILITYIACTOR g2 99.1 99.6 75. 6

14. UNIT CAPACITY I'ACfOR J3,............... 96. 8 99.3 62.2

15. UNIT FORCED OUTAGE RATE J4 ............. 0.9 0.4 4.1

16. SIHJfDQ!5S SCIILDULED OVER NEXT 6 MONIES (TYPE, DATE AND DURATION OF EACII):

March 3 8, 1975 Seismic Restraint Inspection and Maintenance.

June 21 26, 1975 Seismic Restraint Inspection.

17. IF SIIUTDQ18 AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

HOURS RLACI'OR WAS CRITICAL X 100 GRQSS H()URS lN IU I'Ql<'I'IN I'l!IUQD Pq I I AVAILAB]I ITY FAC fQR I IQURS GI;N'.IbYI'OR ON I I. NE X 1 0 0 GROSS HOURS 1N IKPQ!<'I'ERIOD h EI'I.I;.Cll<kCAI. PQÃI!lk ('L'Nl!INI'I":DX MO J3 UNIT CAPACI'H I'ACI'OR I~IAX. IJLPJ!NDA!3[,I; C/Q7ACk'[g X GRQSS IlQURS IN REPORT PI.RIQB FORCED OU'I'AGl', I!OURS X 100 UNI'I'J'I'AGL'ATE IIOUI<S Gl!NL'INI'OR QN LINI! +

I'ORCI',D QUI'AGE I IOURS

.*Changed from EST to DST.

<<>> P

( Ik

~

~

~ ~

~ ~ ~

~ ~

~ ~

~

' ~ ~

~ ~

~ I ~ ~

~ ~ '

I

~ ~

~ ~ I

~ ~ ~

~ ~

~ II

~ ~ ~

0 I Q I I

t

50-250 1

Unit No. 3 was in service con-tinuously from December 28, 1974 until

'OCKET UNIT NA~5 NO.

Turkey Point Unit Mo. 3 February 20, 1975. A reactor trip March!a5 1975 occurred duping a transient condition .

associated with the performance of a PREPARED BY V. T.IChilson ~ r;

. . test of the moisture separator-reheate TELEPHONE 805 445-6211 Ext: 2177--.

sa~n svs REPORT bQAIH February, 1975 U N IT S H U T D 0 N N S /. R E D U C T I0NS

'1 PE, lI IE'IHOD OF F-FORCED DURATION SHUTTING DO/'N

'O DA L S-SGKDULED (HOURS) THE REACTOR' CO~st NTS 02 75 02 02 S N/A Unit load was reduced to test turbine valves. (non-nuclear system) 03 75 02'20 3.2 Reactor tripped by No. 3 C steam generator low level in coinci-dence with steam flow greater than feedwater flow. This was caused by a transient condition associated with the performance of a moisture separator-reheater drain system test. (non-nuclear system) 04 75 02 20 1.5 Turbine tripped reactor No. 3 A steam generator high-high level caused by failure of the feedwater control valve to close.

(non-nuclear system) 05 75.02 20 3 Operating with feedwater control system in-manual during unit start-up. Reactor tripped by. No. 3 B steam generator low level in coincidence with steam flow greater than feedwater .

flow. (non-nuclear system)

• REASO'4 xR $ +'IHQD-A-EQUIPi~lENT FAILURE (EXPLAIyi) 1 ~<DXUAL B-lIAINT. OR TEST 2-iilkXUAL SCRk~l C-REFUELING 3-AUTG~QTIC SCRNf D-REGULATORY RESTRICTION E-OPERATOR TRAINING M3 LICENSE EXSlINATION F-ADAINISTPATIVE

' G-OPERATIONS ERROR H-OTH=R (EXPr.CIN) 75 02 25 B N/A Unit load reduction to clean No. 3 A steam generator feedwatei" pump suction strainer. (non-nuclear system)

0 gl

~4 1 1

~ 4 d>

~

C

DOCKET NO. 50-251 UNIT lhl~fE REPORT M H Februar , 1975 JJA'I'I". March 5, 1975 V. T. Chil son CO~IVLf;"I'fiD IJY

'll'!LL'O ~)<<f

• OPERATING STA'I'US

1. RBPORTING PBRIOU:0001~75 02 01" . 7llROUGII 2400, 75 02 28 GROSS IIOURS IN IU.'POII'I'))4G Pl)RIOI): 57T. 0 *

2. CURREIVfLY AU71IQRIZED PONER 1.1VEL piMt) 22pp hfAX2 DrPEiVD. CAPACI'IY (hfÃ0 iVEI') 666 I')

3. POB'ER I.EVEI TO M.IICH RESTRICTED (IF ANY): (M('e NET) None

4. 'EASONS rQR RESTRICTIONS (Ir ANY): , i.

TIIIS CUhfULA'I'IVE YIQ)VVH YR- TO-DA'fE 'IO l)IITB.

5. Nmr:R OF HOURS TflE REACTOR WAS CRI I ICAL o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t' ~ ~ 671.0* 1 337.6 10 671.4

6. REACTOR RESERVE Sf!UTDQ&f HOURS ........ 97.3 97. 3

7. HOURS GBNBRA7OII ON LIE% ................ 671. 0* 1 317.. 7 10 375.5

8. " UiVIT RESERVE SHUTDQ1% HOURS ........... 9. GROSS TIIERhfAL ENERGY GEhfERATrD(hWH).... 1 448 194 2 830 214 21 182 423

10. GROSS ELECTRICAL ENERGY GENERATED (hi lQ'I) e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 472 834 923 086 6 697 347 J.L ~ . h~i- ELECTiiICAL FRTRvi" GFI~TZv'1TFD (hii'2ri)....450...552 878 315 6 347 431

12. REACTOR AVAILABILITYFACTOR lg......... 100. 0 94. 5 82.3 13 ~ UNIT AvAILAmLITYrACTQR QZ ............ 100. 0 93.1 80.1 UNIT CAPACITY FAC!OR +34 ~ ~ ~ ~ ~ ~ ~; ~ ~ ~ ~ ~ ~ ~ 100.8 -/ 93.2 75. 4

15. UNIT I'ORCED OIJfAGE RATE g4 5.2

16. SIIUTDQI'I'NS SCI.KDULED OVER NEXT. 6 MQVTIIS (TY1'E, DATE AND DURATION OF EACH):

March 24 May 18, 1975 Refueling, Maintenance, and Xnspections.

June 14 19, 1975 Seismic Restraint Inspection.

17. IF SI.IU'I'DOb'N AT END OF REPORT PERIOD, ESTIhfATED DATE OF STAR'IUP:

GROSS ilUVRS IN l(EPOI<TlNG 1'1'RIOD IMT AVAI~ILITYFAVOR = IIOUIKS Gl!IXV.'.INJQR OiV J.INE X 100 j2 ()JOSEY f fQ Jf($ lN Q.IQI(f, IEf(IQ rf.Ec~RIcAL van:.R c,rhlf:I vrr>> x Ioo

" "'"" = Nr.',I hlAX. 'D)if"] Vf)ABJ".I Chl'ADITI'Y

'X GROSS I IOURS IN'REPORT PE!'.IQD UVI'I'iFI'AGI:. IVVI'll = rORCrn ': OIJ~AGI; HOURS llQURS Gf!NfilNI'OR QV f,lNI! +

FOi~CI:II OUIACi; IIOIJIIS X. loo 5/ Unit capacity factor greater than 100%, due to cooler condenser cooling water.

from. EST to

~

~

• Changed DST.

P k

1 h

II 1~

~

v

~ L'NCLOSURE A

~ W DOCKET NO. 50-251

'UNIT NAME Turkey Point Unit No. 4 DA75 March' 1975 COMPLETED BY V; T. Chilson TELEPHONE NO. 305 445-6211 Ext. 2177 DAILY UNIT 'PONER OUTPUT

~1~< Februar 1975

'AY

/

679'0 '77 AVERAGE DAILY Mtlte-net 679 DAY 21 AVEBA(Z DAILY Mfe-net 673 6'87 22 447 681 649 23'4 674 680 683 685 689 684 688 27 "'82 693 28 ,683 10 692 29

• 683 30 616 676 681 NOTE: Daily average power 'level

~

15 684 greater than 666 MWe, due to cooler condenser cool-684 water..

682 681 680

4 ~,

~ t g 4

,><4j 1

f DOCKET NO.

50-251 Unit No. 4 has remained in Turkey'Point Unit No. 4 service continuously since)January 9, 1975. Unit performance has been satis-, DATE March 5, 1975 factory except for load reduction on February 22; 1975 to repair No. 4 C PREPARED BY V. T. Chilson feedwater control valve. TELEPHONE I'305j 445-6211 Ext. 2177 REPORT bGNIH .

February, 1975 U N IT S H U T D'.,0 lit N S / R E D U C T I 0 N S I'YPI: i~1H'IHOD F- FORCED DURATION Ol'HUTTING DATE

'-SCHEDULED (HOURS) REASON. " REACTOR IOLi'HE COi~ÃENTS 02 75 02 22 A. N/A Unit load was reduced to approximate 100 MWe to isolate and repair No. 4 C steam generator feedwater control valve.

(Non-Nuclear System)

REASOil: gIETHOD A-EQUIPi~1ENI'AILURE '(EXPLAIN) 1-~i1ANUAL B-tIAIPV. OR TEST ~dQ SCB C-REFUELING g AtJIGxIATIC SCRA~I D-REGULATORY RESTRICTION E-OPERATOR TRAINING Aha LICENSE EXAMINATION

~

F-AD~iINISTRATlVE G-OPERATIONAL ERROR H-O'IHER (EXPLAIN)

f'