ML20096E038

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Monthly Operating Rept for Apr 1992 for Brunswick Steam Electric Plant,Units 1 & 2
ML20096E038
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/30/1992
From: Rumple R
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20096E031 List:
References
NUDOCS 9205190031
Download: ML20096E038 (9)
v • d • e


Text

,

CPliL CO PLANT PERFORMANCE DATA SYSTEM PAGE 1

RUN DATE 05/05/92 APPENDIX B - AVERAGE DAILY POWER LEVEL RPD39-000 RUN TIME 08:27333 BRUNSWICK UNIT 1 DOCKET NO. 050-0325 COMPLETED BY RONALD RUMPLE TELEPHONE (919)457-2752 APRIL 1992 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 778 17 772 2

778 18 772 3

779 19 770 4

779 20 770 5

778 21 215 6

756 22

-13 7

718 23

-12 8

778 24

-11 9

777 25

-11 10 774 26

-10 11 775 27

-7 12 774 28

-6 13 775 29

-8 1

14 761 30

-12 15 752 16 774 1.16 - 8 9205190031 920500 i

PDR ADOCK 05000324

-4 R

PDR i

O e

CPsL CO PLANT PERFORMANCE DATA SYSTEM PAGE 1

RUN DATE 05/07/93 OPERATING DATA REPORT RPD36-000 RUN TIME 08:39:56 BRUNSWICK UNIT 1 DOCKET NO. 050-0325 COMPLETED BY RONALD RUMPLE OPERATING STATUS TELEPHONE (919)457-2752

1. UNIT NAME: BRUNSWICK UNIT 1 NOTES-There are 560 fuel bundles
3. REPORTING PERIOD: APRIL 92 in the Reactor Coro, 1090 BWR and 3.

LICI'NSED THERMAL POWER (MWT): 2436 160 PWR spent fuel bundles in the

4. NAMEPLATE RATING (GROSS MWE) : 867.0 Fuel Pool, and 108 fuel bundles in
5. DESIGN ELECTRICAL RATING (NET MWE) : 821.0 the new fuel storage vault.
6. MAX DEPENDABLE CAPACITY (GROSS MWE): 791.0
7. MAX DEPENDABLE CAPACITY (NET MWE) : 767.0

~~-----------------------

8.

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

9.

POWER LEVEL TO WHICli RESTRICTED IF ANY (NET MWE):

10. REASONS FOR RESTRICTION IF ANY:

TilIS YR TO CUMUL MONTil DATE ATIVE

11. IlOURS IN REPORTING PERIOD 719.00 2903c00 132551.00
13. NUMBER OF llOURS REACTOR CRITICAL 496.85 2517.88 87881.32
13. REACTOR RESERVE SilUTDOWN IIRS

.00

.00 1647.10

14. HOURS GENERATOR ON LINE 493.10 2487.31 84201.37
15. UNIT RESERVE SIIUTDOWN llOURS

.00

.00 00 16e GROSS THERMAL ENERGY GEN. (MWH) 1177149.25 5896708.27 183021943.70

17. GROSS ELEC. ENERGY GEN. (MWH) 384895.00 1935805.00 60019285.00
18. NET ELEC. ENERGY-GENERATED (MWH) 371633.00 1874548.00 57767878.00
19. UNIT SERVICE FACTOR 68.58 85.68 63.52
20. UNIT AVAILABILITY FACTOR 68.58-85.68.

63.52

31. UNIT CAP. FACTOR.(USING MDC NET) 67.39 84.19 55.31
22. UNIT CAP. FACTOR (USING DER NET) 62.96 78.65 53.08
33. UNIT FORCED OUTAGE RATE 31.42 14.32 15.45
24. SHUTDOWNS SC!!ED. OVER NEXT 6 MONTHS (TYPE, DATE, AND DJRATION OF EACH):

Refueling outage scheduled from 9/12/92 to 12/4/92.

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START UP: 5/25/92
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALI"'Y INITIAL ELECTRICITY COMMERCIAL OPERATION 1.16 - 9

-'a y-

,m.,

,,.~,,v m-+

~~.4

%y,

,n

00CkIT NO.

050-0325 Lit!T M@E Beu-s=tc6 1 CATE Nv 19'2 C0"PLETED BY Rceald E n le TELEPHDME 919-a57-2752 UNIT $HUTDOW45 AND PC'.rER REDUCTICMS REPORT MONTH 4:en 1992 l

r METHCD OF LICENSEE SYSTEM CCMPCatsT CAUSE & CORRECTIVE ACTIDs To DURATION

$MJTTING OCW EVENT CCOE (4.)

CCOE (5)

FREVENT PECURRENCE NO.

DATE TYPE (1)

(. CURS)

REASOM (2)

REACTOR (3)

R! PORT m3.

92-920421 F

225.9' A

1 1-92-12 kB M/A Diesel Generator wall 90-1 was 023 declared inoperable. As a result, busses E-5 and E-6 were declared ie. operable. Because of Tech. Spec.

3.0.3, the Unit was taken to cold shutrbwn.

1:

M 2:

Reesem 3:

Mathed 4:

System Cede:

5:

C e t Ceda F - Forced A-Equipment failure 1-Manual Instructions for lestructions fer S - Scheduled (exp!ain) 2-Manual Scram preparation of data entry p eparation of data B-Maintenance or test 3-Automatic scram sbaets for Licensee Event entry sheets for LER C-Refueling 4-Contim: ' ions Repert (LER) file from file from IEEE Standa-d D-Regulatory.

5-toad tv6 '-eans IEEE Standard 605-1983.

803A-1983, per restriction 6-Other per RUEEG-1022.

MUREG-IC22.Section VI.

E-Operator Training &

Section VI. Item 13.b Itee 13.c License Examination

.F

. Adminf strative G.

Operational error L(explain)

H-Other (explain)

4 CP&L CO PLANT PERFORMANCE DATA SYSTEM PAGE 2

RUN DATE 05/05/92 APPT.9 DIX B - AVERAGE DAILY POWER LEVEL RPD39-000 RUN TIME 08:27:33 BRUNSWICK UNIT 2 DOCKET NO. 050-0324 COMPLETED BY RONALD RUMPLE TELEPilONE (919)457-2752 APRIL 1992 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 594 17 582 3

596 18 581 3

585 19 584 4

583 20 579 5

582 21 171 6

582 22

-12 7

582 23

-11 l

8 577 24

-12' t

9 579 25

-12 10 578 26

-12 11 579 27

-11 12 579 28

-11 13 SLO 29

-10 14 582 30

-6 15 582 16 582 1.16 - 8 l

l 4

-4 l

CP5L CO

" PLANT PERFORMANCE DATA USTEM PAGE 2

  • I RUN*DATE 05/07/93 OPERATING' DATA REPORT RPD36-000 1

RUN TIME 08:39:56 BRUNSWICK UNIT 2 DOCKET NO. 050-0324 COMPLETED BY RONALD RUMPLE OPERATING STATUS TELEPl!ONE (919)457-2752

1. UNIT NAME: BRUNSWICK UNIT 2 NOTES-There are 560 fuel bundles
2. REPORTING PERIOD: APRIL 92 in the Reactor Ceth 1113 BWR and
3. LICENSED THERMAL POWER (MWT): 2436 141 PWR spent fuel bundles in the
4. NAMEPLATE RATING (GROSS MWE): 867.0 fuel pool, and 3 fuel bundles-in
5. DESIGN ELECTRICAL RATING (NET MWE) : 821.0 the new fuel starage vault.
6. MAX DEPENDABLE CAPACITY (GROS 3 MWE): 782.0
7. MAX DEPENDABLE CAPACITY (NET MWE): 754.0 6

IF CHANGES OCCUR IN CAPACITI RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT, s

r" 7E REASONS:

3

9. POWER LEVEL TO WHICH RESTRIC*i": IF ANY (NET MWE):
10. REASONS FOR RESTRICTION IF J' THIS YR TO CUMUL MONTH DATE ATIVE
11. HOURS-IN REPORTING PERIOD 719.00 2903.00 144575.00
12. NUMBER OF HOURS REACTOR CRITICAL 493.83 2378.33 92091.38 i
13. REACTOR RESERVE SHUTDOWN HRS

.00

.00-

.00

14. HOURS GENERATOR ON LINE 492.15 2201.18 87154.67
15. UNIT RESERVE SHUTDOWN HOUPS

.00

.00

.00

16. GROSS THEEMAL ENERGY GEN. (MWH) 931085.97 4196154.21-184126854.86
17. GROSS ELEC. ENERGY GEN. (MWH) 292570.00 1366375.00

_59550469.00

18. NET ELEC. ENERGY GENERATED (MNH) 280694.00 1315104.00 57105576.00
19. UNIT SERVICE FACTOR 68.45 75.82 60.28-
20. UNIT AVAILABILITY FACTOR 68.45 75.82 60.28
21. UNIT CAP. FACTOR (USING-MDC NET) 51.78 60.08 50.18
22. UNIT CAP. FACTOR (USING DER NET)_

47.55 55.18 48.11

23. UNIT FORCED OU'IAGE RATE 29.99 18.45 13.51
24. SHUTDOWNS SCHED OVER-NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EAC;l):
25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START UP: 6/15/92
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):--FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY

~~-~~---

COMMERCIAL OPERATION

a l'16 - 9 i.

(

y

DOCKET NO.

050-0324 t.*IT NAME Erveswick 2 DATE "av I???

c maid prole COMPLETED BY o

TELEDONE

.119-457-2752 l

tNIT SriUTDOVNS AND POWER REDUCTICMS REPORT MONTH kr:1 1992 METHOD OF LICE *SEE SYSTCA COMPGnENT CAdSE & CORRECTIVE ACTIDM TO DURATICR SHUTTING DOWN EVENT C00E (4)

COOC (5)

M EYENT RECtTGPENCE NO.

DATE T'FE (1)

(HOURS)

REASON (2)

REACTOR (3)

REPORT NO.

92-920214 F

0 H

6 e/A TG XC Reacter oower being maintain-d at

. approximately 80% due to certinuing 017 3

electrobydraulic contrcl (LIC)

I syster escillations. The urit remeined at ;his pcwer level until the forced shutdows which began on I

4/21/32 as referenced in event #

92-024 I

1:

Jyge

'2:

Reasen 3:

Wthod 4:

Syste-Code:

5:

Ccrecrent Code F - Forced A-Ecuipment failure Man"al Instructions for Instructions fer 5 - Scheduled (explain) 2-Manual Scram preparaticn of data entry preparatica of data B-Maintenance or test 3-A-to*atic scram s5eets flor Licensee Event entry sheets for LER i

C-Refuel irig 4-Cor;inuations

. Report (LER) file frors file Jrtra IEEE 5%ndard D-Regulatory 5-Lead reductiers IEEE Standard 805-1983 803A-1963 per restriction 6-Other per WREG-1022 NUREG-1022. Sectice: WI.

I E-Operator Train' g &

Section VI. Item 13.b Item 13.c l

Licensa Examination F-Adninistrative G-Opersttorial error (explain)

H-Other (explain)

U h

l.

1 9

DOCKET NO.

050-0324 UNIT MAME eruaswick 2 CATE May 1992 CCW LETED BT Grald W ie TELEPHONE

_2J9-457-2752 UNIT SHUTD0VNS AND POWER REDUCTIONS REPORT MONTH April 1992 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO DURATION SHUTTINC D04N EVENT CODE (4)

C00E (5)

PREVE9T RECURRENCE NO.

DATE TYPE (1)

(HOURS)

REASON (2)

REACTOR (3)

REPORT NO.

92-920421 F

210.85 A

1 1-92-12 NB N/A Diesel Generator ws1190-1 was declared ineperable. As e result.

024 Lusses E-S and E-6 were declared inoperable. Because of Tech. Sgec.

3.0.3, the Unit was taken to cold shutdown. Since repairs to the wall will take several weeks. this evert was closed out on 4/3n/92 at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> and tSe planned cutage to rake repairs to the EHC System. Main Turbir.e. 2B Reactor Feedpump and '5e 4A Feadwater Heater was corunenced at trat time.

l I

1:

Tvre 2:

Peason 3:

Method 4:

Systtm Code:

5:

Component Code F - Forced A-Equipment failure 1-Manual Instructions fer Instructiens for 5 - Scheduled (explain) 2-Manual Scram preparation of data entry preparation of cata B-Maintenance or test 3-Autocatic scram sheets for licensee Event entry sheets for LF7 C-Refueling 4-Continuations Report (LER) file from file from IEEE Standard 0-Regulatory 5-Land reductions IEEE Standard 805-1983, 803A-1983, per restriction 5-Other per NLREG-1022 NUREG-1022 Section VI.

E-Operator Training &

Section VI, Item 13.b Item 13.c License Examination F-Administrative l

G-Operational error l

(expl air.)

i H-Ot',er (explain)

-a

m DOCKD NO.

050-0324 UNIT NAME Brunswick 2 CATE May 1992 COMPLETED BY Renald R:rnole TELE

  • HONE 919-457-2752 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH
  1. pril 1992 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE & CCRRECTIVE ACTION TO DURATION SHUTTING DOWN EVENT CODE (4)

CODE (5) ~

FREVENT RECURRENCE NO.

DATE TYPE (1)

(HOURS)

REASON (2)

REACTOR (3)

REPORT NO.

92-920430

' 5 16.0 '

B 6

~N/A TG XC The Reactor was already in cold l

shutdown due to the inoperability of 025 busses E-5 and E-6 as referenced in event # 92-02a. This event is betr.2 cpened to comence the planned i

outage to repair the EHC System, i

Main Turbine, Reactor Feedpump and l

the 4A Feedwater Heater.

i 1:

Tvoe 2:

Feason 3:

Method 4:

System Code:

5:

C m ent Code F - Forced A.-

Equipment failure 1-'

Manual Instructiois for instructions for S - Scneduled (explain) 2-Manual Scram prey ration of data entry preparation of data B-Maintenance or test 3-Auto:natic scraa sheets for Licensee Event entry sheets for LER C-

Refueling 4-Continuations RepMt (LER) file from file from IEEE Standard D-Regulatory

.5-Load reductions

-IEEE Standard 805-1983, 803A-1983, per E.

Operator Training &..

6-Other per NUREG-1022, NJREG-1022,Section VI.

restriction Sectien VI Item 13.b-Item 13.c License Examination F-

.te inistrative G

. Operational error

'(explain)

H -'

Other(explain)

~

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6 f

n i

9 t'-

}

l j.-

1 4

i

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1 1

1 i

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The fohwing pages are the corrected copies for-thez l-months':of February andLMarch 1992.-

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