ML19210E989

Monthly Operating Rept for Nov 1979

ML19210E989
Person / Time
Site:	Brunswick
Issue date:	12/05/1979
From:	Willis E CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19210E986	List: ML19210E985 ML19210E989
References
NUDOCS 7912130358
Download: ML19210E989 (12)

Text

.

APPENDIX B AVERAGE DAILY POWER LEVEL DOCKET NO.

050-0325 UNIT 3RUNSWICK UNIT 1 DATE 12/C5/79 CCMPLETED BY EULIS WILLIS TELEPHONE 919-457-9521 NOVEMBER 79 DAY A"G. DAILY PCWER LEVEL DAY AVG. DAILY PCWER LEVEL (MWE-NET)

(MWE-NET) 1 776.

17 617.

2 776.

18 685.

3 776.

19 698.

4

749, 20 434.

5 237.

21 0.

6 0.

22 0.

7 0.

23 0.

8 0.

24 0.

9 0.

25 0.

10 0.

26 0.

11 0.

27 0.

12 0.

28 0.

13 0.

29 36.

14 0.

30 515.

15 O.

16 203.

1551 169 9

1.16 - 8 3b 7912130

.X

\\

OPERATING DATA REPORT DOCKET NO.

050-0325 DATE 12/05/79 CCMPLETED BY EULIS WILLIS TELEPHONE 919-457-9521 OPERATING STATUS 7

7 NOTES:

7 7

1.

UNIT !!AME: BRUNSWICR UNIT 1 7

7 2.

REPORTING PERIOD: NOVEMBER 79 7

7 3.

LICENSED THERMAL POWER (MWT): 2436 7

7 4.

NAMEPLATE RATING (GROSS LT): 86 7.0 7

7 5.

DESIGN ELECTRICAL RATING (NET MWE): 821.0 7

7 6.

MAX DEPENDABLE CAPACITY (GROSS 5'E): 815.0 7

7 7.

MAX DEPENDABLE CAPACITY (NET 5'E): 790.0 8.

IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT, GIVE REASONS:

9.

PCWER LEVEL TO WHICH RESTRICTED IF ANY (NET L'E):

10.

REASONS FOR RESTRICTIC" IF ANY:

THIS YR TO CUMUL MCNTH DATE ATIVE 11.

HOURS IN REPORTING PEC OD 720.0 8016.0 23713.0 12.

NUMBER OF HOURS REACTCR WAS CRITICAL 2 76. 3 45 86. 7 16897.3 13.

REACTOR RESERVE SHUTDCWN HOURS 0.0 0.0 1647.1 14.

HOURS GENERATOR ON LINE 238.2 4335.2 15885.0 15.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 16.

GROSS THERMAL ENERGY GENERATED (5'H) 485 146.9 8943005.2 32890196.3 17.

GROSS ELECTRICAL ENERGY GENERATED (MWH) 162303.0 2992928.0 10924205.0 18.

NET ELEC3ICAL ENERGY GI2OIATED (MWH) 150719.0 2867842.0 10506440.0 19.

UNIT SERVICE FACTOR 33.1 54.1 67.0 20.

UNIT AVAILA3ILITY FACTOR 33.1 54.1 67.0 21.

UNIT CAPACITY FACTOR (USING MDC NET) 26.5 45.3 56.1 22.

UNIT CAPACITY FisCTOR (USING DER NET) 25.5 43.6 54.0 23.

UNIT FORCED OUTAGE RATE 66.9 16. 1 21.7 24.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):

Ralief Valve Modification: 79 12 12 120 Hours Refueling: 79 05 30 6 72 Hours 25.

IF SHUTDCWN AT END OF REPORT PERICD, ESTIMATED va d 0F STARTUP: 0/ 0/ 0 26.

UNITS IN TEST STATUS (PRIOR TO CCMMERCIAL OPERATION):

FORCAST ACHIEVED INITIAL CRITICALITY INITIAL CRITICALITY COMMERCIAL OPERATICN 1551 170

Page 1 of 2 DOCKET NO- 050-0125 UNIT SilUTDOWNS AND POWElt ItEDUCTIONS 0

UNIT N AM E lirunsuick #1

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O Dg DATE Ih c"mimr 1974

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p COMPLE1 ED ilY Fulis A. Willis ll q-da(j j d

REPORT MON 11I Noveniber 1979

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TELEPilONE (919) 457-9521 w.

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jY Licensce E r, Causc i Correceive No.

Date g

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Report #

mO Pacven Itecurrence 6-o y

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021 791105 F

262.8 B

3 N/A Cll INSTRU Reactor scranuned because of reactor low level apparently caused by a run-back of the master feedwater flow controller. An operator was in the proc'ess of completing a shifL of the feedwater level controller from 3 element to single element control in

~

order for calibration to be performed on a steam flow instrument.

lie had placed the controller in manual, shifted to slugle element control and placed controller back in automatic control, when the reactor level started to decrease and a scram resulted from low level.

The feedwater level control loop was checked out and no problems were detected.

Procedural changes were i

2 3

4 F: Forced Reason:

Method:

Exinbie G Instructions S: Scheduled A l:quipment Failure (Explain) 1-Manual for Pacparanon of Dau ll Maintenance of Test 2-Manual Scram.

I'nu> Sheets for 1.wensce

~

~

3 Automatic Scram.

Eveni Report (LER) late INURLG-C Refueling W

D-Regulatory Restriction 4 Other (Explain) 01611 W

E Operator Training 1 License Examination F Administrative 5

G-Operational Error (Explain)

Eslaba 1 - Same Source 19/77)

Il-Othe r (E xplain)

N e

Page 2 of 2 DOCKET NO. 050-0325 UNIT SilOTDOWNS AND POWER ltEDUCTIONS UNIT NAME Ilrunswick #1 OA o

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D g-n37c necemnet 1979 3

COMPLEl ED BY Eulis A. WI111s ItEPORT MONTII November 1979 TELEPHONE (919) 457-9521 "i

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Cause & Correceive e

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Action to c$ 5 5

j5 Iteport #

(E 0 0

F Pacvent itecurrence O

made to give more specific instruct-lons on transferring from 3 element control to single element, and back to 3, element control. A caution was also added to minimize this operation abovg 75% reactor power due to_the fast response of the feedwater control system. Overtime was worked.

I 2

3 4

F: Forced Itcason:

Method:

Exinbii G Instru6 ions S: Scheduled A-liguipment Failure (Explain) l Manual for Preparation of Daia m

Il Maintenance of Test 2 M.mual Serarn.

I:nir> Sheeis for Licensee m

C Itefueling 3 Autonutie Scrain.

Esent flepon (LER) h!e (NURI G.

D Itegulatory llestriction 4 Other (Explain) 01olI E Operator Trainingi License Exainination F Adnunistrative 5

C-Operational Error (Explain)

IN!abu 1 Sanie Sousee y

(9/77)

Il Other (Explain) g

A.

^

s page 1 of 2 UNIT SilUIDOWNS AND POWER RLpilC110NS E N.

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DATE December 19M I

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j COhlPLETED iiY Fulls A. Utilis REPORT hIONIll Novembet. 1 179 ELEPil0NE (919I 457-95*1 e.

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}YE Licensee h

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Cause & Couective No.

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5 sj s5 Event

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b 022 791120 F

219 A

3 N/A ED El. ECON The reactor scrammed as a result of the loss of power to emergency husses El and E2.

Offsite power was inter-rupted to El and E2 due to degraded switchyard voltage.

The degraded switchyard voltage condition occurred when the generator exciter was placed In manual voltage control to clear an over-excitation annunciator in accord-ance with the Annunciator procedure.

Apparently an unstable system voltage condition caused a further deterio-ration of switchyard voltage when the exciter was taken out of automat ic voltage control. The outage was extended as a result of the repairs to t'he uninterruptible power supply (UpS) system which failed when power was lost to buses El and E2.

I 2

3 4

F: Forced Itcason:

hiethod:

1:xlobit G - Instsuctiim S: Sthed uled A Eiguspnient Failure (Explain) 1 -hf anual for 15cparation of D.na B-klaintenance of Test 2-htanual Ses.am.

Enisy Sheets for 1.icensee C Refueling 3 Automatic Scrain.

Evens Iteport (LER) File INURLG-m D-Regulaiosy Resirielion 4-Othet ( Explain) 01611 m

E-Opesator Tsaining & IJcense Examination F Administrative 5

G-Operational Enor (Explain)

Exlubia I-Same Source c)/77)

Il-Other (lisplain)

N U

Page 2 of 2 050-0325 UNIT SilUTDOWNS AND POWElt ItEDUCTIONS DOGEl NO.

UNI f NA%1E lirnnswick #1 g h[Ugg orgE becember 197.9_

IIEPOftT hf 0NTil November 1979 CONtPt.ETED E1Y E"lis A. ujilis

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El.EP!!ONE (919) 457-9521 l

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Eicensce E r, Cause & Correceive e

No.

Date

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iteport #

mO

/sevent itesurrence P

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5 (1) The Annunelator Procedure for over-excitation was rewritten to provide a method to clear the alarm under system unstable voltage conditluns.

(2) The UPS system was repairel.

A preventative maintenance program will he initiated to assure that the system is reliable at all times.

(3) A study is in progress to determine how to reduce unstable system condi-tions. Overtime was worked in return-lug the unit to service.

I 2

3 4

F: Forced Itcason:

f.tcihod:

Eslohit G - Instruenons 5: Scheduled A-l'.inipnient Failure (Explain) 14tanual for Picpasanun of Daia Itataintenance or Test 2-htanual Serain.

Ent#> Sheets for 1.ieeniec m

w C !<efucling 3 Antoinatic Scrain.

then: Report (LElti File (NUltLG-g D llegulatory llestriction 4-Othes (thplain) 0161)

E-Opesator Training 1 License Exainination F-AJniinistrative 5

G Operational Error (Explain)

Eshibis I Same Sonree 19!77)

Il Other (thplain) 4

APPENDLX Docket No.: 050-0325 Unit: Brunswick No. 1 Date: November 1979 Completed By: Eulis A. Willis OPERATIO4S SI.TiARY BRUNSWICK NO. 1 Brunswick Unit No. 1 operated at a 26.5% capacity factor for the month of November. The following power changes and shutdowns occurred during the month:

November 5:

The reactor scrammed because of a runback of the master feedwater flow controller.

November 20:

The reactor scrac=ed because of the loss of power to e=ergency busses El and E2.

For more infor=ation on individual outages, see the Unit Shutdowns and Power Reductions Logs (Append 13 D) for the month of November.

Availability factor for the month was 33.1%.

There are 320 BWR spent fuel assemblies and 154 PWR spent fuel assemblies stored in the BSEP #1 spent fuel pool.

1551 175

APPENDIX B AVERAGE DAILY POWER LEVEL DOCKET NO.

050-0324 UNIT 3RUNSWICK UNIT 2 DATE 12/04/79 COMPLETED BY EULIS WILLIS TELEPHONE 919-457-9521 NOVEMBER 79 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWE-NET)

(57.-NET) 1 726.

17 640.

2 723.

18 770.

5 734 19 288.

4 736.

20 0.

5 735.

21 75.

6 735.

22 472.

7 734.

23 6 19.

8 735.

24 470.

9 710.

25 740.

10 421.

26 75 1.

11 544.

27 717.

12 696.

28 789.

13 759.

29 799.

14 750.

30 780.

15 755.

16 751.

1551 176

1. 16 - 8

OPERATING DATA REPORT DOCKET NO.

050-0324 DATE 12/04/79

, COMPLETED BY EULIS WILLIS TELEPHONE 919-457-9521 OPERATING STATUS 7

y NOTES:

7 7

1.

UNIT NAME: 3RUNSWICK UNIT 2 7

y 2.

REPORTING PERICD:

NOVE!GER 79 y

y 3.

LICENSED THERMAL POWER (MWT):

2436 7

1 4.

NAMEPLATE RATU;G (GROSS ET):

367.0 t

1 5.

DESIGN ELEC"'RICAL RATING (NET MWE): 821.0 7

1 6.

MAX DEPENDABLE CAPACITY (GROSS MWE): 8 15.0 y

7 7.

MAX DEPENDABLE CAPACITY (NET 5'E): 790.0 8.

IF C3ANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT, GIVE RIASONS:

9.

POWER LEVEL TO WHICH RESTRICTED IF ANY (NET 5'E):

10.

REASONS FOR RESTRICTICN IF ANY:

THIS YR TO CUMUL MONTH DATE ATIVE 11.

HOURS Di REPCRTING PERIOD 720.0 30 16.0 35737.0

~

12.

NCISER OF HOURS REACTOR WAS CRITICAL 689.3 5435.9 24724.1 13.

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 14.

HOURS GENERATOR ON LINE 668.4 5 145.3 23274.4

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 16.

GROSS THERMAL ENERGY GENERATED (5'H) 1416365.2 9935082.7 42382917.0 17.

GROSS ELECTRICAL ENERGY GENERATED (5'H) 474035.0 3346490.0 14162817.0 18.

NET ELECTRICAL ENERGY GENERATED (5'H) 459354.0 3215017.0 13603229.0

19. UNIT SERVICE FACTOR 92.8 64.2 65.1 20.

UNIT AVAILABILITY FACTOR 92.8 64.2 65.1 21.

UNIT CAPACITY FACTOP. (USING MDC NET) 80.8 50.8 48.2 22.

UNIT CAPACITY FACTOR (USING DER NET) 77.7 48.9 46.4

23. UNIT FORCED OUTAGE RA;E 7.2_

6.0 13.2 24.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

Relief Valve Modification: 79 12 26 120 Hours Refueling: 79 02 15 2184 Hours 25.

IF SHUTDOWN AT END OF RE? ORT PERIOD, ESTIMATED DATE OF STARTUP:

0/ 0/ 0

26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL.0PERATION):

FORCAST ACHIEVED INITIAL CRITICALITY INITIAL CRITICALITY COMMERCIAL OPERATION 1551 177 n

H

s DOCKET NO.

050-0324 O OD P UNIT S!!UTDOWNS AND POWER REDUCTIONS f"[]ll /j -

/) g UNIT NA%IE 11runswick #2 g']){/p DATE December 1979 sJm j

CONIPLETED 11Y Fulis A. Willis REPORT MONTlf November 1979 TELEP!!ONE (919) 4 57-9521 E

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$g 3

$ $3 Licensec Eg h

C.iuse 1 Cus teetive No.

Date Q

5@

5 is5 Event g,'d pU Action su H

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Itcport #

mO Picvent llecurrence o

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023 791119 F

51.6 11 3

N/A ZZ ZZZZZZ Reactor scrammed on a high ptessure signal which was attributed to an instrument rack being jarred by Jani,torial personnel while cleaning the floor in the area of the instru-ment. rack.

Cuard rails will be placed around all sensitive instrument racks to minimize the potential for bumping. Janitorial personnel have been instructed to not clean around instrument racks unless specifically requested. Overtime was worked in returning the unit to service.

I 2

3 4

F: Forced Reason:

Mcihod:

Exlobin G Insituccious S: Scheduled A li uipment Failure (Explain) 14tanual fus Preparation of Daia i

ll Maintenance of Test 241anual Scram.

Entr> Sheets for Licensee 7

C Itducting 3-Autunatic Serain.

Esent l<epors (LER) file (NUREG-D-Regulatory Restriction 4-Ot he r ( E xplain) 01611

~

E Opciatur Training 1 License Examination N

F-Adnunnt rative 5

CD G-Operational Es cur (Explain)

Eshibit I Same Sousee (9/77)

Il Other (Explain)

UNIT SilulDOWNS AND POWER REDUCTIONS DOCKET NO. 050-0124 0 [] /] g

()

UNII~ NAM E Bruimwick #2 (f

D DATE December 1979 COMPLEl ED 11Y Eul 1, A _ W f I I i <a d

REPORT MONTil November 1979-TELEP!!ONE (91'O 457-9521 w.

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Licensee

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Cause 1 Correceive N...

Daie e,

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2ge Eve,n y

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357:

Repost #

Eu gu Pseveni Recurrence g

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o 022 791109 1

35.0 A

1 N/A IIC IITEXCil Power was reduced to repair condenser

~

waterboxes A-South, li-North.

Water-boxes were inspected for leaks using the belium leak detection method. A total of 94 leaking tubes were plugged in A ; South box.

Itepairs were inade to leaking joint on li-North waterbox but were not effective in stopping leak.

Plant Engineering is investigating methods of repairing joint leak in 13-North waterbox at a later date.

This box remains in service by control-ling water level just below the top of box.

Overtime was worked.

I 2

3 4

F: Forced Reason:

Method:

Exinhis G-Instruaions

~

S: Scheduled A li uipment Failure (Explain) 1-Manual for ISeparaison of Daia t

U' 11 Maintenance of Test 2 Manual Scram.

I nu> Sheets for 1.ieemee W

3 Automatic Scram.

Eveni Repon iLER) File (NURLG-C !<efueling D Regulatory Restrielion 4-Ot her ( Explain) 01611 E Opciaior Trainmg & License Examination

~

F Adminisitative 5

N G-Operational Error (Explain)

Estabii 1 - Same Source W

pi!77)

Il Other (Explain)

APPENDIX Docket No.: 050-0324 Unit: Brunswick No. 2 Date: November 1979 Completed By: Eulis A. Willis OPERATIONS

SUMMARY

BRUNSWICK NO. 2 Brunswick Unit No. 2 operated at a 80.8% capacity factor for the month of November. The following power changes and shutdowns occurred during the month:

November 9:

Power was reduced to repair condenser waterboxes A-South, B-North.

November 19:

Reactor scra=med because of an instrument rack being jarred by janitorial personnel.

For = ore information on individual outages, see the Unit Shutdowns and Power Reductions Logs (Appendix D) for the month of November.

Availability factor for the month was 92.8%.

There are 132 BWR spent fuel assemblies and 98 PWR spent fuel assemblies stored in the BSEP 42 spent fuel pool.

Due to a transcribing error, the number of PWR spent fuel assemblies stored in BSEP 42 should have read 91 instead of 84 spent fuel assemblies for the month October 1979.

1551 180