ML20080T943

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Monthly Operating Repts for Jan 1984
ML20080T943
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 01/31/1984
From: Chapman M, Jones G, Thom T
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8403020103
Download: ML20080T943 (41)
v • d • e


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.- ' 16 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-2 59 UNIT I DATE COMPLETED BY M. Chapman TELEPHONE 205/729-0834 MONTH Januar:r 1984 DN'! AVERAGE DAll.Y POWER LEVEL DAY AVER AGE DAILY POWER LEVEL IMWe Net) IMWe Net)

-l _

-10 17 690 117 18 816 2 .

319 707 3 39 _

4 340 20 736 469 21 894 5 -

242 1055 6 22 7 -11 23 1023 g 564 1045 24 662 1042 9 33

~

s 10 776

  • 26 1046 919 27 995 11 974 529 g; _ 33_

-13 899 29 597 931 30 845 I4 986 3, 1022 _

15 909 l-INSTRUCTIONS On this format, list the average daily unit power lesel m MWe Net for ca h day in the reporting month. Compute to the nearest whole megawatt.

. 19I77) 8403020103 PDR,ADOCK 05000259 640131 R PDR 3

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- 17 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 UNIT DATE 2/1/84 COMPLETED gy M. Chapman

~' ' -

205/729-0834 TELEPHONE

-MONTH January 1984

-U DAY - AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe. Net) 1070 ,7 1079 073 .

1080 2-

,3 1074 1079

- 1077 20 1062

_4

'1072 251 p- 21 1065 -14

  1. m 6 22 -

7' 1036 23

-12 g, 747 24

-12 E '943 134 9,

10 1072 26 765 1077 959

-:- 37 g '1071 28

'1063 982

/; 13 29 1C46 984 34 ,

- 30 848 1053 15 ";- 3, r 1040 16 I' -

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INSTRUCTIONS

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Ca'th'is format. list the average daily t: nit power lesel in MWe Net for each day in the reporting month. Compute to 4 - , the nearest whole rregawati.

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18 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 3

UNIT DATE COMPLETED BY Ted Thom TELEPHONE 205/729-0834 MONTH January DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) gyw,.ger, F 7

- ,3 -5 17 _

-6 2- -7 gg ,

-7 3

-7 g, -6 4 -6 20 -6

.5 ._

-6 23

-7 6

-6 -6 22

~0 -7 7 23 __

-5 -6 8 24 9 25

-3

-6 ~

10 26

-6 -3 11 -- 27 ,

-2 12

-5 yg .

-6 13 29 -3

_3 14 30 -3

-6 -3 15' . 3,

-II 16 ._

F INSTRUCllONS On this format, list the average daily unit power lesel in Mwe Net for each day in the reporting month. Compute to the nearest whole megawatt.

  • (9177)

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, OPERATING DATA REPORT y . t

- DOCKET NO. 50-259 DATE 2/1/84

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COMPLETED BY M.chnnmnn

> TELEPHONE 205/729-0834 s.

. OPERATING STATUS sN Browns Ferry - 1 Notes ik ' Unit Name:

-52. Repoiting Period:

'Janusry 1984 3293 L 3.' Licensed Thermal Power (MWt):

1152

14. Nameplate Rating (Gross MWe):

- 5; Design ElectricaI Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

1098.4-1065

7. Maximum Dependable Capacity (Net MWe):

-W _ 18.T If Chynges Occur insyCapacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:

N N/A

9. Power Level To which Restrict d.If Any(N t MWe): N/A
10. Reasons For' Restrictions.Il Any: N/A ,

1 p

This Month Yr..to Da:e Cumulative 83.306 I1. Hours in Reporting Period . 744 744 727.68 727.68 50,533.80

> 12. Number Of Hours Reactor Was Critical l

0 0 5,785.02

' 13.; Reactor Reserve Shutdown Ilours 49,404.87

' 687.23 687.23

- 14.- Hou'rs Generator On-Line 0

~

0 0

15. Unit Reserve Shutdown Hours 1.625.642 1.625.642 140,183.321 .

,16.L Gross Thermal Energy Generated (MWH) 546.640 546,640 46,192,260

'17 Gross Electrical Energy Generated (MWH) , , ,

' 18/ Net Electrical Energy Generated (MWH) 533.247 533.247 44.858.574

- 92.4' 92.4 59.3

'19. Unit Service Factor - 59.3 92.4 92.4

20; Unit MailabiHty Factor . 50.6 67.3 67.3 2l c Unit Capacity factor (Using MDC Net). 50.6 67.3- 67.3

' 22. Unit Capacity Factor (Using DER Net)' 23.6

~

3. 5 - 3.5 yJ ;23.' _ Unit Forced Outage Rate

- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date,and Duration of Eachl:

+ .

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. ! 25/ If Shut DownSt End Of Report Period. Estimated Date of Statup-

' 26. Unih in Test s'tatus (Prior io Ccmmercial Operationi: F orecast Achiesed

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% , 4 INITIA L CRITICALITY f

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i INITIA L ELECTRICITY _._

COMMERCIAL OPER ATION t

P b s (9/77) y1

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sr OPERATING DATA REPORT DOCKET NO. 50-260 DATE 2/1/84 COMPLETED BY M. Chapman TELEPHONE 205/729-0834 OPERATING STATUS '

Notes Browns-Ferry - 2

'I.2 Unit Name:

January 1984

2. Reporting Period.

2

3. Licensed Thermal Power (MWt): 1793
4. Nam.eplatt am;ing(Gross MWe): 1152

~ 5. Design Electrical Rating (Net MWe):

1065

6. Maximum Dependable Capacity (Gross MWe)s 1098.4
7. Maximum Dependable Capacity (Net MWe):-

1065

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:

N/A

9. Power Level To which Restricted.!! Any (Net MWe): N/A

'10. Reasons Foi destrictions,If Any:

N/A

~

This Month Yr..to-Date Cumulative 744 744 78.247

11. hours in Reporting Period 655.22 655.22 50,619.40
12. Number Of Hours Reactor Was Critical .

88.78 88.78 13,989.14

13. Reactor Reserve Shutdown Hours 640.17 640.17 49.133.01

.14. Hours Generator On-Line 0 0

15. Unit Reserve Shutdown llours > ._0 2,033,033 2,033,033 142,178,078
16. Gross Thermal Energy Generated (MWH) 47,257,568 660,300 660,300

!!7;1 Gross Electrical Energy Generated (MWH) ,

45,900,651 642,048 642,048

18. Net Electrical Energy Generated (MWH) _ o2.8 86.0 86.0
19. Unit Service Factor 86.0 62.6 86.0
20. Unit Availability Factor 81.0 ~81.0 55.1 J 21. Unit Capacity Factor (Using MDC Net) 81.0 81.0 55.1
22. Unit Capacity Factor (Using DER Net) -

0.4 0.4 24.5

-23. Uniit Forced Outage Rate

-24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):

July 1984 n

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

' 26) Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIA L CRITIC *.~ ?TY - _

INITIA L ELECTRICITY COMMERCIAL OPER ATION (9/77)

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.~ . . . . . . . . , . . . ... -- .. . _ . _ . . . , . , . . . . , .

21 OPERATING D ATA REPORT DOCKET NO. 50-295 _

D\TE ? 1 R 'i CONIPLETEP BY red Thom TELEPilONE 20;/7^Q n834

~

OPERATING STATUS Browns Ferry -3 Notes

1. Unit Name:
2. Reporting Period: January 1984
3. Licensed Thermal Power (51Wt): 3293
4. Nameplate Rating (Gross SIWE): 1152 l S. Design Electrical Rating (Net 51We): 1065 l
6. Stasimum Dependable Capacity (Gross 31We) 1098.4
7. Stasimum Dependable Capacity (Net 51We): 1065
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Siace Last Report.Give Reasons:

N/A

9. Power Level To which Restricted,If Any (Net 51We): N/A
10. Reasons For Restrictions, if Any: N/A _ _

This 51onth Yr .-to-Dat e Cumularise II. Ilours in Reporting Period 744 744 60.672

12. Number Of flours Reactor Was Critical 0 0 43,087.80 0 0 3,878.13
13. Reactor Reserve Shutdown liours __
14. Hours Generator On-Line 0 0 42,193.71
15. Unit Resene Shutdown Itaurs 0 0 0

! 16. Gross Thermal Energy Genera:ed (51WH) 0 0 126,307,711 17 Gross Electrica! Ene;y Generated (51Wil) 0_____. 0 41.597.620

. 18 Net Electrical Energy Generated (51WH) 0 0 40,375,256 0 0

19. Unit Senice Factor 69.5

= 20. Unit Asailability Factor 0 0 69.5 0 0 62 3

21. Unit Capacity Factor (Using \tDC Net) l 2.' Unit Capacity Factor (Using DER Net) 0 0 62.5
23. Unit Forced Outage Rate _

0 0 16.4

24. Shutdowns Scheduled Oser Nest 6 51onths (Ty pe. Date, and Duration of Each)

l June 1984 _

i.

3 25 If Shut Down At End Of Report Period. Estimated Date of Startup-

26. Units in Test Status t Prior to Commercial Operation) I orecast Ac hies ed INII'l AL CRillC ALIIY

[ INITIAL ELECTRICITY CO\l%1ERCI \L OPER \IlON a

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3

I 9

. DOCKET NO. 50-259 '

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME . Browns Ferry-1 DATE 2/1/84 COMPLETED BY el. Chapman January 1984 ~

- REPORT MONul TELEPHONE 2G5 /729-083':

f h, Cause & Corrective

, .!'E 3 Y Licensee Event

,E,vo u? 93 . Action to N"- DJte & 3? s .zi s 5 rE C Prevent Recurrence l

  • $E $ yo 5 g Report :

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6 -i 31.75 4 EOC-5 refuel cutage l 264 1/1/84 -S C 265 1/16/84 F 20.65 11 1 Reactor acram due to a bad rod j

pattern.

F A "A", "B", and "C" string high-pressure 266 1/13/84 heaters isolated

.U Control rod sequence exchange.

267 1/27/84 S IT 3 4 l 2 l Method: Exhibit G Instructions F: Forced Reason:

for Preparation of Data S: Scheduled A. Equipment Failure (Explain) 1-Manual 2-Manual Scram. Entry Sheets for Licensee B-Maintenance of Test C Refueling 3 Automatic Scram. Event Report (LER) File (NUREG.

D-Regulatory Restriction 4-Other ( Explain) 0161)

E-Operator Training & License Examination 5

F-Administrative G-Operational Error (Explain) Exhibit I - Same Source (9/77) Il-Other (Explain)

T

DOCKET NO. 50-260 UNITSl1UTDOWNS AND POWER REDUCTIONS UNITNAME Browns Ferry-2 DATE . 2/1/54 M. Chapman COMPLETED BY January 1984 REPORT MONTH TELEPHONE 205/729-0834

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- E E jg ' E*o Cause & Corrective E_ g 3 j .E 5

.g g 5 Licensee Event D ', h? Action to No. Date g 3g s Prevent Recurrence 3: $ j;g g Report = in O j' 6

B Derated for turbine control valve test 284 1/7/84 S and SI's.

Derated for control. rod pattern adjust -

285 1/14/84 S H ment.

Reactor scram during performance of u 286 1/21/84 F 2.78 G 3 Main Steam Line High Radiation SI, on W "B" channel when "C" channel was tested the MSIV's closed. Arparent cause of scram was failure to reset

101.05 H Unit remains down for scheduled main-287 1/21/84 S tenance after scram.

Derated for control rod pattern 288 1/30/84 S H adjustment.

' 3 4 1 2 Exhibit G Instructions tiesson: Method:

F: Forced 1 Manual for Preparation of Data S: Scheduled A-Equipment Failure (Explain) Entry Sheets for Licensee B Maintenance of Test 2-Manual Scram.

3 Automatic Scram. Event Report (LER) File (NUREG-C-Refueling 0161) 4-Other (Explain)

D-Regdatory Restriction E-Operator Training & License Examination 5

F A41ministrative Exhibit I - Same Source G-Operational Error (Explain)

Il-Other ( Explain) 19/77)

T

7

-6 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. ' 50-296 :

  • UNIT NAME Browns Ferry-3 DATE 2/1/84 COMPLETED BY Ted Thom January 1984- "

REPORT MONTH TELEPHONE 205/729-0834:

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, .!E h . .Y h Licensee - 5to h*L Cause & Corrective No. Date g 3g s 2g5 Event  ? -93 Action to dE $ Report
  • NU E'- Prevent Recurrence 5

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140 1/1/84 S 744 C 4 EOC-5. refuel cutage continues (controlled shutdown) w

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I 2 3 4 F: Forced Reason: Method: Exhibit G -Instructions S: Scheduled A-Equipment Failure (Explain) l-Manual for Preparation of Data B-Mairitenance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source 19/77) Il-Other ( Explain)

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MECliANICAL in1NTEGNCE SU;0fARY f csse Eculi".tEUT - -

For the. Month of EJanuary 19 84 ,

ACTION TAKEN EFFECT ON SAFE ~ TO PRECLUDE CAUSE OF. RESULTS.OF' COMPONENT NATURE OF. OPERATION OF.. RECURRENCE DATE SYSTEM MALFUNCTION" MALFUNCTION' MAINTENANCE Tile' REACTOR Normal Use. Leak MR 216605 l-3 -' HPCI Flow Element- Torque flanges None-1-FE-73-033 Assembly Error.. CRD.18-03 would not Installed solenoid 1-4 CRD Scram Pilot. - Repair Valve None spring correctly.

SCRAM

' Valve- MR .214352 1-FSV-85-39A-Insufficient. pumping Corrected impeller-None Personnel' Error-1-4 Core Spray 1A PSC Pump Adjust-capability clearance-Impeller MR 150699 l

Insuf fic.icnt pumping Corrected impeller Adjust' None Personnel Error 4 Core Spray 1B PSC Pump capability clearance Impeller MR 150698 Normal Use Damaged wire rope Replaced wire rope Control Bay Wire. Rope 'None m 1-5 MR 150742 u Elevator Replacement hone Unknown 511ssing mounting Installed bolts l-10 RB Venti- 1-FSV-64-021' Install bolts bolts MR 201520 lation Solencia Valve Unknown Leak Replaced seal 1A PSC Pump Seal Leak None 1-11 Core Spray I t'R 214378

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r MECHMICAL K\1NTETANSE SU!DfARY-psse EotrIrMENT .

2 19'84 ,

~ ' '

For'the Month'of f: January -

.. ACTION TAKEN EFFECT ON SAFE ,

.TO PRECLUDE;

!CAUSE,OFi .,

RESULTS OF-

OPERATION OF"

-COMPONENT. NATURE OF' P.ECURRENCE-DATE SYSTEM- MALFUNCTim ~ MALFUNCTION-

' MAINTENANCE ~THE REACTOR Reworked-. piping, Improper piping- Broken flange ~on Standby- 3D. Diesel Replace. cooler 'None cooler hcod; MR-150709 1-4< ~

head ~.

connection:-

Diesel. Generator. '

Cenerator Engine Cooler ,

Door' not operatin;;

~

Adjpstedrand

' Adjust and,

^

None Normal'use. Lubricated, 1-11 Door Door 248 smoothly ~

Interlock ~ lubricate ~ MR'220726- . .

Erratic pressore' Nonc Disassembly' None No malfunctioni 'MR 215896-Metrix Valve l

1-11 ,EECWf found

' 3-PCV-67-79

! Replaced valves Normal use CRD 38-47 would not.

Directional Replace .None- withdraw MR 201572-1-13 CRD Control Valves EP 120 and.122 . t}

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- '. FR$L*'IS' FFRRY - NUCLEAR' PLANT ' C'
IT 3,)

7 I CSSC'EQl?IPMENT' !1ECTRICAL 3*AINTENANCE.SD: MARY

-[

9/29/82 j For.the Month,of January 19 84 ._ .:

(-

~

Action.Taken ~

~ Nature of. EffectonSafel

. Operation of 'Cause.of Results'of ,  ; To .Prce lu'de I

_Dite 's Svstem' Component'- Maintenance The Reactor I Malfunction Malfunctfon'  ! Recurrence 3983 _

l 10/29 Radiation 0-PMP-90-0152B Replace motor None Bad motor. Motor pulling high l Replace bad pump monitoring B; sample pump current. motor, MR 218434-1

'12/l' Diesel 0-BDCG-254-000/ Replace nylon None' . Supplied'by Broken b'olt alerted Replaced nylon 125 Volt DC bolts, nuts vendor ?Ji of the problem hardware wit'i and flatwashers .

brass, with brass MR 202260: o

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bP M S FERRY tit *CLsan PLA;;T:Di1T 1 FLECTRI C.\L - 2:AI;;TENA;;CE ' S C Sf.tRYI -

'CSSC Ef}t'IPMEN - . 9/29/a2 lI'orl the Manth of : January -19 84-

.r-  : Ef f ect on Saf e .[ Action Taken j

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.(

Nature of' Operation of Cause.of Re.sults'ef I To Prcclude lg, The Reactor-

~

' Mr.1 f unc t ion

?!al func t lori Fecurrence-E-Date

  • 1Syster Component  : Maintenance

.l l 1983? Buzzer will' sound but Replace bad card.

Replace None: Bad' annunciator

12/13 innunciator 1 - 11 S - 5 5 - 4 .

card' will not reset Panel 9-4 MR209032:

~

and Sequen- annunciator tial ". vents card ,

Recorder l.

I 1984 Motor running' noise Replace bad motor, l-FAN-064-0012I. Replace motor, .None Bad motor.

1/7' RB IIcating' '

!s and Venti- Exhaust lA E 2M187 .

lating System' . . .

Possibly laborers LER-259/84001 . I.' Manually ' stopped Residual 1-PMP-74-39 Inadvertent None 1/9 start working la. area the pump, g deat bumped the start MR'131979 Removal push button None Bad detector Smoke detector alarm- Replaced smoke-1/21 High Pres- L-XA-39-26B Replace smoke detector, per -

detector ing sporadically '

sure Fire formed SI4.1.1.C..

Protection and 4.1.1.C.S.

System MR*207406 None . Unknown Relay R2B did not LER 259-84006.

1/26 RB lleating 1-PDS-064-0062 None p::ck up and Venti- MR 256391 lation System F T

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2 ELECCI Cf.L ;M.\i :It':IdCE1 SLTL\RY s

- CSSCI D!UIPMENT -- . , 9/29/32:

4, 9 . . . . , . . , . .

cFor ths: Month ofDJanuary 19 84' '

1 i

.Effect on Safe' .

.letion Taken

'Results"of. To Preclude-Naturesof OperationDof . lCause.of' j j. ..Svnte=- .

Component Maintenance The: Reactor. Malfunction: 'Malfu$ct ion- LRecurrence-7,,_Sa t e - '

,.2983 MIN: type (fuses? 'None' ' Replaced'old; type',

111/21 Control' Panels (25-25' Replace. fuses (None. fuses MIN-3 with-are no' longer-I Rod Drive A through H '

used at BFNPt ,

new ATM-3.

s

- MR 130665-y 1984-1/8. Reac. tor 2-XS-71-000 Perform- LER BFRO-50-260/:

SI 4.5.F.1.D&E None Drift in set. Failed SI 4.5.F.1..

Core Iso-points D&E- 84001.

lation ^

~

Cooling- ,MR 216757 i.

None- Bad relay' Equipment status Replace: bad relay.

1/12 Annuncia- 2-XX-55-003 Replace-relay

~

tor & Se-'

display will not MR 213827- .U light up quential so Events Recorder Water level above Neg ground of -100V Replaced bad coil 1/21 250V DC 2-FSV-73-8' Replace coil on None'.

'and mercury bulb.

FSV73-8 and coil, unknown on Rx MOV 2A RMOV mercury bulb why bulb failed MR 207102 on LS-73-8 Smoke detector alarm- Replace smoke.

t High Tres- 2XA-39-27E Replace' smoke- None Bad detector f 1/21 ing dete'ctor.

f Sure Fire detector l

Protection MR 207099

.. System f None Bad detector Smoke detector alarm- Replace smoke de-High Pres- 2XA-39-27C Replaced smoke tector. Performed' 1/21. ing Sure Fire detector-SI 4.ll.C.165.

Protection MR-207208 System Bad-coil ,Rx LO-LO H2 O level Replaced bad coil 7 RB Heating ~ 2-RLY-064-16AK..C Replace coil None l 1/27 not operating MR 256742 l

& Ventila- 7 i

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L BP.0*-3S J F2S KO NCCENsR I PLANT. UNIT '.3' BF EMSIL 30:

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"" E-CSSC E0P!PMENT -ELECTRICAtltAIN !: NANCE <SCt' TAR

,9/29/82' ..

- For ' the >!Onth wf__ January . 19* .84:

.)

" Effect on Safe,- ;i Actiun Taken

}

. Nature of. Operatior . of - - ' Cause '.o f ~ Results of' 'To Prcelude'

i Malfunetion' Recurrence E Date System -Component- ' Maintenance 'The Reactor' i Malfuncttan" Bad contacts Chiller motor.would Teplace contacirsT; Air Condi- 3-CHR-031-- - Replace motor None

'( 1983 '

.not start

,B 12/8. tionin -1976 . starter con- '

MR 216105~

1r System tacts Annunciatorf.in con- Replaced bad smoka CO2 Storag's 3-XS-39-36 . Replaced smoke None' Bad deter. tor trol room will not detector.

-[.1984 Fire Pro- detector-yj4 clear MR 214732 tection Bad relay Abnormal alarm Replaced bad rela:

1/5 Diesel 125 3-CHG8-254- Replace relay: None I

Volt DC 000AA MR 214819 Bad smoke detector Failed SI 4.ll.C.1 Replaced bad smokc CO2.Storag4 2 3-XS-39-93JA _ Replace smoke. None 1/15 &C5 detector.

& Fire ' detector Protection n2M3M' Worn reset switch Difficult to operate Replace resat and' CO2 Storag a 3-00-39-00 Replace reset None 1/19 and broken' guide' reset; defective circuit breaker, Fire Pro- Panel 25-324- switch and circuit breaker sleeve on breaker breaker-tection MR.212248 3 and Purg- CBI ing System Bad coil Relay fails to p'ck Replaced bad coil RB Heating 3-RLY Replace coil None 1/25 up .LER 296/84002 and Venti- 16AK37 lation MR 207939 System ~

Bad smoke detecto r Detector intermit- Replaced bad 1/28 3-XA-39-71YA Replace detector None CO2 Stor- tently alarming detector.

p age Fire -

Protection MR 207801 and Purg-ing. System Replaced bad 1/28 3-XA-39-71YL. Replace detector None . Bad smoke detector Detector intermit-CO2 Stor- tently alarming, detector.

age Fire .

l MR 207941 Protection 7

1 .

and Purg-

? ing System .

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~~ i 32 FIELD SERVICES

SUMMARY

January 1984 Work Synoosis

'The unit 3 cycle 5 outage continued during January. The principle work

. performed during the January report period involved the Residual Heat Removal L(RHR) beat exchanger work, refuel floor and torus attached piping. Furlough of temporary employees was begun on January 23,1984 (completed 1/27) in an effort to reduce the work activity level to the minimum necessary to support contractor support commitments.

Maior Wort Areas A. Refuel Floor - Blade guide removal work began-on January 4, along with the arranging of the camera for vessel inspection on unit 3 Two shipments of blade guides to Peach Bottom were completed during the month with the prep-aration for a third shipment in progress. On January 9, the first shipment of new fuel for unit 31was received. This work continued through the month. _ On January 19, work on the refuel floor was interrupted due to limit switch problems on the overhead crane. The crane was repaired and returned to service on January 26. The flushing of the unit 3 recircula-

- tionLnozzles was completed during the month ( ALARA work for dryw'all inspe ctions) .

B. Turbine - The unit 3 "c" low-pressure turbine work continued during January. The cover was set, horizontal joint bolts installed, and assembly I

completed by January 9, 1984. The "A" turbine lube oil cooler was

. assembled, placed in service, and checked for leaks on January 10, 1984.

. The rotor was received from the service shop on January 11 for the unit 3

ys
.

.. s. l .+

33 ,

= FIELD SERVICES

SUMMARY

- January 1984-Ma.ior Work Arena (Continued)

'B. Turbine (Continued).

feedpump turbine "A". Assembly of the front standard was completed on l January 21. along with 'the checking of the coupling alignment. -

1C. -Other Mechanical-Work -

1. Turbine lube -oil coolers were probologged. "A" cooler was completed on January 5, and 69 tubes were found to need plugging. - "B" cooler was completed on January 9 and 49 tubes were found to need plugging.
2. The offgas'precooler was probologged on January 18. No tubes were found to require plugging.

3 H ler8 were probologged on January 19. ;No tubes were found to 2

crequire plugging.

4. - Main Steam Relief Valve (MSRV) - The 13 relief valves had their flanges machined.' Quotes were. received from Target Rock on January 15 for MSRV' cartridge rebuild. Other MSRV work continued.

'5 'Changeout of 63 Control Rod Drive (CRD)' rods was completed along with

rebuilding of spare rods.
6. 00245 Replacement of Hydraulic Snubbers was completed during the month.

RHR heat exchanger work continued during January. Probolog of "B" 7 V heat exchangers was completed by January 15. There were 62 tubes identified for possible plugging. Awaiting resolution of plugging, this number coupled with previously installed plugs may be excessive.

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FIELD SERVICES

SUMMARY

January 1984 Maior Work Areas (Continued) p C. Other Mechanical Work (Continued)

.7 (Continued) ~

' Probolog of "D" heat exchanger was completed on January 24. Three

tubes were found to need plugging. Floating head gaskets for RHR heat exchangers are urgently needed and curraatly on order.
8. Work continued on outboard and inboard is -

9 Valve 3-75-50 was repaired satisfacterily.

' 10. ' Repair work was performed on 64-series valves during the month (disassembly).

~ D. Electrical / Instrumentation

1. Motor-generator:(MG) set maintennace-work continued during the month.

MG set "3A" is 98-percent overall complete with. "3B" is 85-percent overall complete.

2. ' Recirculation Motor Maintenance - Work continued during the month.

r Reassembly on recirculation pump motor "A" is 95-percent overall complete. "B" has had the thrust bearings, guide bearings and thrust collars cleaned and inspected. Work is 50-percent overall complete on "B".

3 P0533 Torus Temperature Monitoring work is continuing. Some holes for

.s:

instrument work have been cut. Work is being delayed dt'e to mounting details not being receive.d fcr instrument installation.

g .

35 ,

FIELD SERVICES

SUMMARY

January 1984

  1. - ('

Maior Work'Arams (Continued) fD. 1 ElectricaOInstrtmentation

" 4.- PO415 Temperature Instrumentation - Work is continuing and was 47-

' percent complete.through January 22 when crews were reassigned to support. removal of welding leads from the torus.

5.- IHSI -- Preparation of temporary electrical service for IHSI work con--

tinued. On January 28, a plant perimeter outage was taken to install ,

.a 4 kV-line..

6. :PO422LInstallation of Reactor' Protection System (RPS) cabinets and conduit began 'on January 18. Circuit' protection panels were prepared lforecenduit. Hangers were fabricated and installed.

-7.. P0392 Scram Discharge-System modification Prefabrication work continued while piping cuts were deferred. Work plans are still in

. review cycle for both mechanical and electrical portions of this work.

E. . Planning and. Scheduling:- Emphasis' has been placed on devehpment of a restart' schedule for. unit 3 cycle 5 outage effort. With the exception of

^

-relected major work items, most of the productive outage work on unit 3 was 5 topped January 27, 1984 due to a' work force reduction in the number of temporary Trades and Labor personnel. This was done as a management effort

.w

~ to ooncentrate on training and compliance activity for both supervisory V

-- 't perronnel and' craft.

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Torus internalmodiilcation work was near completion at the end of the January ~ report period. Sandblasting and coating work is sciteduled to begin in February.-

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bcq : .I, 1 The.following are corrected: Operating Data Reports for the month of-

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Corrected OPERATING DATA REPORT DOCKET NO.

50-260

+

DATE 1/1/84 H LOMPLETED BY Ted Thom TELEPilONE 205/729-0834 OPER ATING STATUS

' ~

, g ,TUnit Name: " " N '~

72. Reporting Period:

Deceinber 1983

3. Licensed Thermal Power (MWt): 3293
4. Nameplate Rating (Gross MWe):

1152

5. Design Electrical Rating (Net MWe):

1065 3

1098.4

~

6. Maximum Dependable Capacity (Gross MWe):
7. Maimum Dependable Capacity (Net MWe): 1065 M. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report.Give Reasons:

N/A

'~

- 9. Power Level To Which Restricted.If Any (Net MWe): N/A

10. Reasons For Restrictions.If Any: N/A ,

This Month Yr.-to Date Cumulative

--II. llours in Reporting Period 744 8,760 77,503 12[ Number Of Hours Reactor Was Critical 722.9 6,670.71 49,964.18 21.1_ 215.54 13,900.36

- 13. Reactor Rewrve Shutdown Hours

14. Ilours Generator On-Line . 710.08 6,517.39 48,492.84 0 0 0
15. Unit Reserve Shutdown I' lours 5 16. Gross Thermal Energy Generated (MWH) : 2.221,550 19,735,198 140,145,045 * .

17 Gross Electrical Energy GeneratM (MWil) 741.540 6.572.380 46.597.288 721,370 6,385.528 45,258,603 th. Net Electrical Energy Generated (MWH)

19. Unit Service Fa'etor 95.4 74.4 62.6

~ 20. Unit Availability Factor 95.4 74.4 62.6

21. Unit Capacity Factor (Using MDC Net) . 91.0 68.4 54.8 91.0 68.4 54.8

. 2L Unit Capacity Factor IUsing DER Net) 4.6 5.3 Z4.6

23. Unit Forced Outage Rate _

=

24. Shutdowns Scheduled Oser Next 6 MonthsIType. Date and Duratioa of Each):

F

~ 25. IIShut Down At End Of Report Period. Estimated Date of Startup:

. 2h. . Units in Test Status lPrior to Commercial Operation): Forecast Achieved INITI A L CRiflCALITY INITI AL El.ECTRICITY-COMMERCIA L OPER ATION (9/77)

(( 3 }

. Corrected OPERATLNG DATA REPORT DGCKLI NO. 50-259 DATE 4 COMPLETED BY Ted Thom TELEPHONE ?ne;/7?o_nR54

- OPERATING STATUS .

Notes Browns Ferry'- I

.1. Ohit Name:

2." Reparting Period:

December-1983 9

3. Licensed Thermal Power (MWt): 2 1.8. Nameplate Rating (Gross MWe):

1065 i 5. Doign Electrical Rating (Net MWe):

1098.4

6. Masimum Dependable Capacity (Gross MWe):

1065

7. Masimum Dependable Capacity (Net MWc):

A If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report Give Reasons:

N/A

. 9. Power Level To Which Restricted,if Any (Net MWe): N/A

10. Reasons For Restrictions.lf Any: N/A This Month Yr.-to Date Cumulative 744 82 760 82,562
11. Hours in Reporting Period 53.33 '2,416.58 49,806.12 12.- Number Of Hours Reactor Was Critical ,

0 47.71 5,785.02

13. Reactor Reserve Shutdown Hours

- 14. Hours Generator On-Line 0 2,317.52- 48.717.64 0 0 0 l15. Unit Reserve Shutdown llours

  • 0 6,784,675 138,557,679 C8 16. Gross Thermal Energy Generated (MWH) 0 2,244,900 45,645,620

.17. Gros 5 Electrical Energy Generated (MWH) 44,325,327 0 2,175,548 (18. Net Electri'al Energy Generated (MWH) 0 26.5 59.0

. 39, Unit Service Factor

'- O 26.5 59.0

20. Unit Availability Factor; '

23.3 50.4 6 21 Un.'t Capacity Factor (Us ng MDC Net) 0 23.3 50.4

" 22. Unit Capacity Factor (Uting DER Nei) _ 23.8 0 8.1 23: Unit Forced Outage Rate

24. Sh'utdowns Scheduled Oser Next 6 MonthqTypej Date.and Duration of Each):

F

. 25. lf Shut Down At End Of Report Period.Extimate! Date of Startup:

n 26. UnM in Test StatuqPrior to Commerci.n Operationi:

Forecast Achieved INITIAL CRITICA LITY INITIA L ELECTRICITY _.

COMMERCIAL OPER ATION (9/77I C g - -~

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I; +

+

TENNESSEE VALLEY AUTHORITY

- Browns- Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama. 35602 i FEB -101984 Nuclear Regulatory Commission Office of Management Information

. and Program Control

< Washington,~DC

_ 20555' cGentlemen:

. Enclosed is the January 1984 Honthly Operating Report to NRC for Browns

' Ferry Nuclear. Plant Units i, 2, and 3 Very truly yours,

' TENNESSEE VALLEY AUTHORITY

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. Power ant Superintendent Enclosures

>cc: Director, Region'II INPO Records Center Nuclear Regulatory Commission Institute of Nuclear Power

. Office of Inspection and Enforcement Suite 1500 .

'101-Marietta Street 1100 Circle 75 Parkway

~ Atlanta, GA 30303 (1 copy) Atlanta, GA 30389 Director, Office of Inspection and'Enforcemett

. Nuclear Regulatory Commission Washington, D. C. ,20555 (10 copies)

Mr. A. Rubio, Director--

Electric Power Research Institute-P. O. Box 10412 Palo Alto, CA 94304 4

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, An Equal Opportunity Employer

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TENNESSEE VALLEY AUTHORITY

DIVISION OF. NUCLEAR ' POWER BROWNS FERRY NUCLEAR PLANT r

A MONTHLY OPERATING REPORT TO NRC Ja'nuary '1,l 1984.- January 31, 1984 w

,1

" DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUl!BERS DPR-33, DPR-52, AND DPR-68 E..

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Submitted by: t 1

- /A D O P1' ant Su intendent h _

TABLE OF CONTENTS 1

Operations Summary. . . . . > . . . . . . . . . . . . . . . . .

- Refueling LInformation . . . L . . . . . . .-. .. .. . . . . . 3

[Significant Operational Instructions. . . . . . .'. . . . . . 5 Average Daily Unit- Power Level. . . . . . . . .. . . . . . . 16

. Opera ting Data Repor ts. . . . . . . . . . . . . . . . . - . . .

- 19 Unit Shutdowns and Power Reductions . . . . . . . . . . . . . . 22 Pl a n t Mait n' e na nce . . . . . . . . . . . . . . . . . . . . . . . 25

- Field Services Summary. . . . . . ... . . . . . . . . . . . . 32 Addenda ' . . . . ... . .......... . .. . . .. .. 36 k

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  1. m m

,1 y Ocarations Summary January 1984 The following summary describes the significant operation activities during

~ the reporting period. In support of this summary, a chronological log of s!.gnificant . events is included in this report.

There were 13 reportable occurrences and-three revisions to previous report-able : occurrences- reported to the NRC during the month of January.

Unit 1 The unit ended its end-of-cycle outage on January 2,1984 when it tied back on the system.

There was one scram on the unit during the month. On January 6, during

.. star tup , the ' turbiDe was tripped because of high vibration. Nuclear

. engineer and operaters bypassed the rod worth minimizer to reduce power more quickly; the' control rod group was not maintained, so the reactor was manually scrammed.

Unit 2

-There was one scram on the unit during the month. On January 21, during main steam isolation valve (MSIV) testing, "B" channel was still isolated when "C" channel was isolated,. causing the MSIV's tc close and scrammed the-reactor. p Unit ~4 The unic.was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage..

Prepared principally by B. L. Porter.

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, , 2

' Operations Su===vy (Continued)

January 1984

~

' Fatteue Usama Evaluation

' -4 -The : cumulative' usage factors for the reactor vessel are as follows:

Location Usane Factor Unit 1 Unit 2 Unit 9 I Shell at water line 0.00592 0.00483 0.00403

- Feedwater nozzle 0.28446 0.20956 0.15429

-C1'osure. studs 0.23343 0-17169 0.13233 NOTE: . This accumulated' monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.

Common System

Approximately.1 52E+06 gallons of waste liquids were discharged containing

' - . approximately 9 40E-01 curies of activities.

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^

Ooerations Summarv (Continued)

January 1984 Refueline Information Unit-1

- Unit 1 ended its fif th refueling outage on Janaary 2, 1984. Unit 1 is

!" - scheduled for its . sixth refueling beginning on or about February 8,1985 with a1 scheduled . restart date of August 25, 1985. This refueling will involve loading 8x8R (retrofit) fuel; assemblies into the core, replacing recirculation piping, work on "A":and "B" low-pressure turbine, upgrade hangers and anchors, a n d. enyironaentally qualify. instrumentations.

There are 764 ' fuel assemblies in the reactor vessel. The spent fuel stor-age': pool presently lcontains 252 EOC-5 fuel assemblies, 26 0 E00-4 fuel

- assemblies; 232 EOC-3 fuel assemblies; 156 'E00-2 fuel assemblies; and 168 E00-

- 1 fuel ~ assemblies. The present fuel pool capacity is 3,471 locations.

Unit 2 Unit 2 is scheduled -for its fif th refueling beginning on or about June 8, 1984 with a scheduled restart date of November 8, 1984. This refueling outage will involve loading additional 8X8R (retrofit) fuel assemblies into the core,

~

. finishing the torus modification, ~ turbine inspection, finishing piping

inspection, l finishing THI-2 modifications; post-accident sampling facility tie-

" ins, - core spray change-out, and feedwater sparger inspection.

h There are 764 ' fuel assemblies in the reactor vessel. At the end of the m'o nth : there were : 248 E00-4 ' fuel assemblies, 353 E00-3 fuel assemblies, 156 IEOC-2 fuel assemblies, and 132 E00-1 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 861 locations.

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^ 0oerations Su=arv (Continued) l

~ )

' ^

January 1984 1 y: ' -

Unit '4 -

T Unit 3' shutdown for its fif thlefueling outage on September 7,1983, with .

,- 4

.ascheduledrestartdateofHayk,~1984. This refuelirig involves loading 8X8R

.g (retrofit) as qmblies into the . core, finishing the torus modificationa, post-

- accident M sampling facility . tie-in, core spray change-out, . finishing TMI-2

-_.  ; modifications, turby ne ir,apection, piping inspections for cracks, and change-out. of jet pump holdMown' beams.-

= There ar i o'0 !fue11 assemblies presently in the reactor vessel. There are

~

Q1 } new; fuel- sssemblies, - 764 EOC-5 fuel assemblies, 280 E0C-4 fuel assemblies,

[ ,124[EOC-3; fuel Sassemblies, 144 ' EOC-2 ' fuel assemblies, and 208 EOC-1 fuel y z;_: ' // -

' assemblNs:inf the spent fuel' storage _ pool. The' present available capacity of the apent fuel pool is 307 locations.

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Stantrinant 0nerational' Events Dr ta'  : Time Event-f Unit 1 11/1 0001- . Reactor thermal-power at 7-percent (%) and holding for startup (water 1 quality out-of-limits). EOC-5 refuel

< outage continues.

0145 - Commenced rod withdrawal for starup.

0445 1 Rolled main. turbine to 100 rps vibration trip.

0505 ' Rolled main - turbine to- 100 rpm.

20515-  ; Manual trip main turbine.

0518- ' Rolled main turbine to -1800 rpm.

0631- Mainiturbine -tripped, high-vibration #4 bearing.

. Reactor thermal power at 225, holding due to turbine vibrations.

1010 Commenced reducing thercal power to obtain three bypass valves.

1500- ~ Rolled main turbine.

.1600 - Reactor thermal power at 12%.

-1629 - Reactor mode' switch to startup, inserting control rods.

1630 Tripped . turbine (vibration) .

.1820 Commenced rod withdrawal from 6% power to obtain three bypass valves.

2000- Reactor power,at 15%, holding startup due to turbine vibration.

1/2 0630 Rolled. turbine to 1800 rpm.

0745- Synchronized generator, commenced power ascension.

1125 . Unit offline ~ for overspeed test on main turbine.

1130~ Turbine overspeed test - trip at 1943 rpm.

1134 Main turbine tripped on high vibration off. #7 bearing.

1147 Synchronized generator, commenced power ascension from 215 thermal power.

11215- . Stopped power ascension at 245 and reducing power.

Startup testing 'in progress.

.2400: , Reactor- power at 21% .

.1/ 3 - -0100 Commenced rod withdrawal for startup.

0410: . Holding power at 29% for condensate domineralizer

problems.

0505 Commenced power ascension from 295' power.

'0520: Stopped power ascenrion at 385 for scram timing control 4 crods.(RTI 5).

1215: RTI'5 in progress, reducing thermal power from 384.

- 2330, '

c reactor power at 345 for RTI 5 4

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6 p-[ Sinnificant Onerational Events 1

t Data T4ma~ Event

. Unit 1 ,'ontinued)

1/ 4' 1410 RTI 5 complete, commenced power ascension from 34%

power.:

1/5- '

0300!' ' Reactor thermal power at 54% for startup testing.-

104501 "A". recirculation pump motor / generator (M/G) set out-of-

. service for maintenance, reducirg thermal power.

1 '0500' Reactor power at 45% for "A" recirculation pump M/G set maintenance. (Brush check)

. Increasing thermal power from 425, "A"

.0530, . recirculation

~~. pump out for maintenance.-

, 3 '06004 Reactor . thermal' power at 455 for "A" recirculation pump

- a '

M/G set maintenance.

0905'+ -Reducing thermal power to place "A" recirculation. pump in service.

1000 Reactor thermal power at 36% to place "A" recirculation pump in service.

"A" recirculation pump in service, commenced power

-1010

., ascension.

~

1052 "B". recirculation pump M/G sat out for brush check, increasing thermal power from 375.

e 1300; Reactor thermal power at 44% for "B" recirculation pump g- M/G set brush check.

L 1340 - commenced reducing thermal power to place "B" recirculation pump in service.

'1400 - Reactor. power at 38% .for placing "B" recirculation pump

,. . .in service.

.1415; "B" recirculation pump in service, commenced power ascension.

~

11500

. Reactor power'at 54% for 'startup tests.

23001 '

Reactor power at 47% due to turbine vibration problems.

1'/ 6 - 0945' commenced reducing thermal power for a controlled

~

4 . shutdown for turbine balancing (vibration problems).

g 1425: 0~  : Unit offline from 14% thermal power.

11500 Reactor thermal-power at 13% holding for turbine D- < -

- ; n balancing.

, t2130 ',

Rolling main turbine.

'g 2330 . Tripped turbine due to high vibrations. -

p l,

2333 n  :

commenced reducing thermal power from 13% to go on

. I '

-bypass velves.

2341. . Reactor. Scram (manual) No.168 from 13% power due to a

" bad rod pattern.

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5 . 7 Sfanificant Onerationni Events Data Tim

  • Event Unit 1 (Continued) 1/7 0925 Commenced rod withdrawal for startup.

1155 Reactor Critical No. 190.

1300 Brought reactor to suboritical for maintenance on control rod 10-5~..

1700 Maintenance complete on control rod 10-51, commenced rod withdrawal for startup.

1705-Reactor Critical No.191, holding up to time control rod 10-51.

2335 Rolled turbine / generator.

1/8 0020 Synchronized generator, commenced power ascension.

0254 Stopped power ascension at 38% for turbine vibration checks.

0600 Commenced power ascension from 38% thermal power.

1/ 9 0700 Reactor power at 70%, startup test in progress.

1700 Reactor power at 66%, startup test in progress.

1730 Commenced power ascension for SI 4 3.B.1.a (Control Rod Coupling Integrity. Check).

1830 SI 4 3.B.1.a complete, reactor poner at 71% for startrp tests. .

1/10 0700 Reactor pouer at 69% for startup test.

0850 Commenced power ascension from 59% power.

1000 Commenced PCIOMR from 71% thermal power.

-1800 "B" and "C" string high-pressure heaters isolated, reduced thermal power from 915 to 76%.

1830 High-pressure heaters back in service, commenced power l

ascension.

1900 Commenced PCIOMR from 84% thermal power.

2055 Removed "C1" and "C2" high-pressure heaters from cervice for maintenance - at 85% thermal power.

vi 1/11 2200 "C1" and "C2" high-pressure heaters back in service, commenced PCIOMR from 84% thermal power.

"A" and "C" string high-pressure. heaters isolated at 975

-1/12 1710 thermal power, reduced thermal power to 875 "C" string high-pressure heaters back in service but "A" b

1715.

string continues to isolate.

1745: "B" string high-pressure heaters isolated.

- 1750 "B" string high-pressure heaters back in service.

?

,-, , . , _ _ , . ~ . . . - - - - -. , . . _ , __ -_ , - _

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1 4 '

. i Sinnificant Onerattional Events

-y Data Tima' Event

'+ Unit 1 (Continued)

~

L1/10, 1800L  ; Reactor power at 905 due to problems with high-pressure (Cond ' heaters.-

'" <1910. "A" and "B" string high-pressure heaters again isolated, reduced reactor. power to 725.

1945' L All high-pressure heaters back in service, commenced

-power ascension. ,

2000 . Commenced PCIOMR from 895.. thermal' power. 1

'0010 . "B"'and "C" string high-pressure heaters isolated.

1/131 reduced' thermal power from 935 to 855.

0200 "B" and "C" string high-pressure heaters back in service commenced FCIOMR from.855 power.

-0340: "4," "B," and "C" string high-pressure heaters isolated, *

' V commenced reducing thermal power from 875

,
0400 L Reactor thermal power at 60% due to isolation of high-

, pressure heaters.

, '0455 'All high-pressure heaters in service, .sommenced power ascenaion.

. 0600 Commenced PCIOMR from 835 thermal power.

-1040 = Stopped PCIOMR at 875 power to remove "A1" and "A2" hesters from service for maintenance.-

j 1/14 0425) "A1" and l"A2" high-pressure heaters back in service, holding at- 875 power- for turbine control valve test and t .

SI's. .

. 0614- Turbine control valve test and.SI's complete, holding at 875 power due to'high-pressure heater. problems.

-1000 "B1" and '"B2" high-pressure heaters out-of-service for

' maintaining, holding thermal power at 875.

2000' Increased' thermal power to 905, high-pressure heater

limited.

- 2230 Reduced thermal power to 875, high-pressure heater limited.. '

N 2400 . Reactor. power at' 885, hich-pressure heater limited.

l.

1/15 '0001 Commenced PCIOMR from 885 thermal power.

Reactor power at 935 high-pressure heater limited.

'.0900 1100 Reactor power at 925, high-pressure heater limited. l' "B" and "C" string high-pressure heaters' isolated, f,

1620 reduced thcrual power to 725.

"B" and "C" string high-pressurc heaters in service, a

3[ 1710-commenced power ascension. -

1730., Ccamenced PCIOMR from 905 thermal power.

P s

W

,g 2

.. L.', Q&$ h ;.,.;. ~ ,

4 . . . . . . _ . , _ . - . _ _ _ . . , . - . - . . ,

7 1 . 9 Stanificant Ocerationni Events Date Tina Event Unit 1 (Continued) 1/16 0019 "B" and "C" string high-pressure heaters and "C" string 10w-pressure heaters isolated. Reduced reactor power from 965 to 885 0030 "B" and "C" string low-pressure heaters back in service, reactor power at 875 0430 Isolated "C" string high-pressure heaters for maintenance.

0435 "B" string high-pressure heaters isolated, reduced thermal power to 80%.

0515 "B" and "C" string high-pressure heaters back in service, commenced power ascension.

1430 Commenced PCIOMR from 845 thermal power.

1500 Stopped PCIOMR at 855 thermal power ("B1" high-pressure heater alarm in).

2230 Commenced PCIOMR from 85% power.

1/17 0245 "B" high-pressure heaters isolated.

0246 "C" high-pressure heaters isolated.

0248 "A" high-pressure heaters isolated.

- 0250 Reduced thermal power frc= 895 to 72%.

0317 All high-pressure heaters back ir, service, reactor power at 75% and holding.

1600 Reactor power at 76%, high-pressure heaters limited.

2200 Reactor power st 77%, high-pressure heaters limited.

1/18 - 0947 Commenced reducing thermal power due to high-pressure heater problems.

1000 Reactor power at 73%, high-pressure heaters limited.

1625 Commenced reducing thermal power due to problems with "B" high-pressure heaters.

2100 Reactor power at 67%, "B" high-pressure heaters limited.

1/19 0800 Reactor power at 69% , "A" high-pressure heaters limited.

- 0927 Commenced reducing thermal power to remove "A" high-pressure heaters from service.

1100 Reactor power at 61% , "A" string high-pressure heaters out-of-service.

1345 "A" string high-pressure heaters in service, commenced I' power ascension.

2015 Commenced reducing thermal power from 78% due to problems with "CF high-presenre heaters.

2100 Reactor power at 73% , "C" high-pressure heaters limited.

V

$ *$ n Wl $9 \#

P 10 .

Stanificant Ocarational Events Date Tina Event Unit 1 (Continued) 1/19 2238 "C" high-pressure heaters isolated, reducing thermal (Cont) power.

' 2400 Reactor thermal power at 715, "C" high-pressure heaters limited.

. - 1/20 1000  : Reactor power at 70% , "C" high-pressure. heaters limited.

2200 Commenced power ascension from 70% power.

2300 Reactor power at 72% , "C" high-pressure heaters limited.

1/21 0535' "C" high-pressure heater'. in service, commenced power ascension.

1500 Commenced PCIOMR from 885 thermal power.

1/22 1100 Reactor thermal power at 1005, maximum flow, rod limited.

. 1200 , Reactor thermal power at 99%, maximum flow, rod limited.

1400 Reactor thermal power at 98%, maximum flow, rod limited.

>1900 Reactor thermal power at 97%, maximum flow, rod limited.

1/23 0200- Reactor thermal power at 965, maximum flow, rod limited.

0410 Commenced reducing thermal power for SI 4 3.A.2 (Control Rod Exercise).

0500 Reactor power at 94% for SI 4 3.A.2.

0530 SI' 4 3. A.2 complete, commenced power ascension.

0700 Reactor thermal power at 975, maximum flow, rod . limited.

.1500 Reactor thermal power at 965, maximum flow, rod limited.

1/25 .0700 Reactor thermal power at 975, maximum flow, rod limited.

1/ 26 1500' Reactor thermal power at 965, maximum flow, rod limited.

1/27 2100 Commenced reducing thermal power for a control rod sequence exchange.

2400 Reactor thermal power at 46% for .a control rod sequence exchange.

1/28 0020 Increasing thermal power, control rod sequence exchange in progress. I-

+ MM b m e e n - e a -s--- ww - ymw -w- -----

4-

11 Stanificant Onarstional Events Date Tina Event Unit 1 (Continued)

. 1/29 0100 Reactor thermal power at 57%, holding for TIP maintenance.

0900 Increasing thermal power from 57%, awaiting TIP maintenance.

2130 Commenced power ascension from 60% thermal power.

.1/30 0130 Cossenced PCIONR from 70% thermal power.

1/31 1500 Stopped PCIOMR at 97% due to condensate demineralizer

" problems, reducing power.

~2030 Commenced PCIOMr from 96% power.

2140 _ Reactor power at 975, maximum flow, rod limited.

'2400 Reactor power at 975, maximum flow, rod limited.

l'

, ot '

s

I .

12 .

Stanificant ODerational Events Data Tina Event Unit 2 1/1 0001- Reactor thermal power at 965 and reducing for turbine control valve test and SI's.

~0100 . Reactor power at 955, turbine control valve test and SI's in progress.

0230. Turbine control valve test and SI's complete, commenced power ascension.

.0300 Reactor thermal power at 1005, maximum flow, rod

^.

limited.

1/3 0700. Reactor thermal power at 99%, maximum flow rod limited (100% electrical).

1/6: '2300 Reactor thermal power at 995,- maximum flow, rod limited

( 995 . electrical) .

.1/7 2155 Commenced reducing thermal power for turbine control valve test and SI's.

1/ 8 0200 Reactor power at 66% for turbine control valve test and SI's.

0445 Turbine control valve test'and SI's complete, reducing thermal power for control rod pattern adjustment.

0500 Beactor thermal power at 62% , control rod pattern adjustment in progress, increasing thermal power.

1730 Control rod pattern adjustment. complete, commenced PCIOMR from-72% power.

1/10 .0430 Reactor thermal power at 100% , maximum flow, rod limited.

1/11 0700 Reactor thermal power at 995, maximum flow, rod limited.

1/12 2400 Reactor thermal power at 99%, maximum flow, rod limited.

1/13' 0700 Reactor power at 985, maximum flow, rod limited.

Commenced reducing thermal power for control rod pattern

~

1/14 2130 adjustment. l<

-1/15 0300 Reactor thermal power at 74% for control rod pattern adjustment.

0630 -Control rod pattern adjustment complete, commenced PCIOMR.

2,1 is . 13

.o Sinnificant Onerational Events Date ' Time' Evant Unit 2 (Continued)

- 1/16- 1500 Reactor - thermal power at 1005, maximum flow, rod limited.-

4 1/17 0700 Reactor thermal power at 995,' maximum flow, rod limited (100% electrical) .

1/18- - 0100 Reactor.. thermal power at 100% , maximum flow, rod

. limited.'

- 1/20 1200 ' Commenced reducing. thermal power due to problems with

. oondensate domineralizers.

1300 Reactor thermal power at 925, condensate demineralizers limited. . .

.1450 Commenced power ascension from 925 thermal power.

2100 Reactor thermal' power at 100% , maximum flow, rod

- limited.

1/21 0255 Commenced reducing thermal power for turbine control valve test and SI's..

0315- Reactor thermal power at 91% for turbine control valve

' test and SI's.-

0345 ' Turbine control valve test and SI's complete, commenced 3 power ascension..

10515 Commenced PCIOMR from 93% thermal power.

-0553 Reactor Scram.No.149, from 945 thermal power during performance of SI 4.1. A-10 (Main Steam Line High Rad) following testing of the "B" channel. When "C" channel

- was tested, the MSIV's closed, scramming the reactor. ' .

-The most likely cause of the Group I isolation was fail-ure'to reset "B"-channel PCIS. The unittwill recain offline for a scheduled maintenance outage.

0840  : Commenced. bringing reactor to cold shutdown.

L b 1940? ' Reactor in cold shutdown.

G .

Commenced rod withdrawal for startup.-

[ L1/24 2038-37 2240 . Reactor' Critical No. 160.

r

.~ 1/25 - l0750- . Rolled turbine / generator. "

LJ 0800 . Turbine tripped, EHC problems.

0815  ? Rolled turbine / generator, rs ;0907" Manually tripped turbine for maintenance on EHC load L

'> se t.

c1322- Rolled turbine / generator.

- 1343 - Synchronized generator, commenced power ascension.

9 1430 Stopped power ascension, CRD 42-31 will not withdraw, reactor power at 25%.

I-r t L'

,e wM M . 3 pyh er e.

l ' y2 -

,,'-.--------v~

w.

, . - - . , , - , - , , . - n . ,>.,-,.,.nn,,,,-,,,.-,,.n... , . ,---v----,- ,-n-- - -, - , .-,, , -- r ,-

14 ,  :

Sinnificant Ocarational Eventu

' Data Tima Event Unit 2 (Continued) 1/25 -1710 Maintenance complete on CRD 42-31 commenced power (Cont) .

ascension ~from 24% thermal power.

2140- Stopped power ascension at 53% power for a. TIP set.

1 1/ 26 0305- Commenced power ascension from 53% thermal power.

1100 Commenced PCIOMR from 78% thermal power.

- 1/ 27 0610- - Received low low water level alarm and 1/4 isolation

. when 16AKIC relay failed. Stopped PCIOMR at 86% power.

0930 Commenced PCIOMR from 86% thermal power.

1950 Reactor thermal power.at 945, maximum flow, rod limited.

"9 1/28; 0255 Commenced reducing thermal' power for SI 4.1. A.10 (Main yp '  : Steam Line High dadiation).

_ 0300 Reactor. power at 92% for SI 4.1. A.10.

4-

0335- Commenced reducing thermal- power for SI 4 3.B.1.a (Control Rod Coupling Integrity).

0342 Reactor power at 90% for SI 4 3.B.1.a.

0345" Completed SI 4 3.B.1.at commenced power ascension.

'0400- - Reactor thermal power at 935, maximum flow, rod limited.

1300 ' Reactor. thermal power at 925, maximum flow, rod limited.

s

'1/29 -2300 Reactor thermal power at- 915, maximum flow, rod limited.

b 11/30. 0235 Commenced power increase for SI 4 3.B.1.a.

0400' Reactor power at 935, maximum flow, rod limited.

2205 - Commenced reducing thermal power for a control rod pattern adjustment.

-2400; Reactor thermal power at 65% for control rod pattern adjustment.

Control rod pattern adjustment complete, commenced power

~

.1/31. .0040 ascension.  ;

Commenced PCIOMR from 925 thermal power.

0145 1200 Reactor. thermal power at 100% , maximum flow,- rod p ,

~ limited.

2400 Reactor -thermal power _ at 1005, maximum flow, rod

-limited. I-2 s

1 I

,e

-e

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n

- - 15 Stanificant Onerationni Events Data' - T4== Event Unit 3 End-of-cycle 5 refuel outage in progress.

1/1 0001' 1/31 -- 2400 End-of-cycle 5 refuel outage in progress.

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