ML20100R505
| ML20100R505 | |
| Person / Time | |
|---|---|
| Site: | Brunswick |
| Issue date: | 03/31/1992 |
| From: | Rumple R, Spencer J CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9204150287 | |
| Download: ML20100R505 (9) | |
Text
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CD&L tmwummmarunnassemenmaamage Carolina Power & Light Company
[
r h m u m o a cesr a fJa: W p M U Brunswick Nuclear Project P. O. Box 10429 Southport, NC 28461 0429 gyn 10 W2 FILE:
B09 135100 U.S. Nuclear Regulatory Commission Washington, DC 20$55 Attn:
Document Control Desk BRUNSUICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS. 50 325 AND 50 324 LICENSE NOS. DPR-71 AND DPR 62 MONTilLY OPERATING REPORT Ger'tlemen:
In accordance with Technical Specification 6.9.1.11 for the Brunswick Steam.
Electric Plant, Unite 1 and 2, Carolina Power & Light Company herewith submits the report of operating statistics and shutdown experience for the month of March 1992.
Very truly yours,
)
Spencer, Gens d Manager W.
Bt ick Nuclear Project 90 004'..MSC Enclosures cc:
Ms. D. M. Aslett Mr. T. C. Bell Mr. R. M. Coats Mr. S. D. Ebneter Mr. M. D.11111 lir. N. B. Le Mr. W. R. Murray Mr. R. C. Oehl Mr. R. M. Parsons Mr. R. L. Prevatte Mr. R. B. Starkey Mr. F. Yost INPO
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CP&b CO PLANT PERFORMANCE DATA SYSTEM PAGE 1
. RUN DATE 04/03/92 APPENDIX B - AVERAGE DAILY POWER LEVEL RPD39-000 RUN TIME 07:41:25 BRUNSWICK UNIT 1 DOCKET NO. 050-0325 COMPLETED BY RONALD RUMPLE TELEPHONE (919)457-2752 MARCH 1992 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1
-16 17 779 2
-15 18 716 3
-13 19 434 4
-14 20 510 5
-12 21 777 6
596 22 777 7
775 23 779 8
778 24 779 9
778 25 779 10 777 26 779 l'
778 27 779 13 777 28 779 13 777 29 759 14 778 30 779 15 777 31 778 16 778 1.16 - 8
CP6L CO PLANT PERFORMANCE DATA SYSTEM PAGE 1
RUN DATE 04/03/92 OPERATING DATA REPORT RPD'36-000 RUN TIME 15:08:20 DRUNSWICK UNIT 1 DOCKET NO. 050-0325 COMPLETED BY RONALD RUMPLE OPERATING STATUS TELEPl!ONE (919)457-2752 1.
UNIT NAME: BRUNSWICK UNIT 1 NOTES -There are 560 fuel bundles 2.
REPORTING PERIOD: MARCH 92 in the Reactor core, 1090 DWR and 3.
LICENSED THERMAL POWER (MWT): 2436 160 Pwn 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
~~-------------e---------
8.
IF CilANGES OCCUR IN CAPACITY RATINGG (ITEMS 3 T!!RU 7) SINCE LAST REPORT, GIVE REASONSt 9.
POWER LEVEL TO WHICH RESTRICTED IF ANY (NET MWE):
- 10. REASONS FOR RESTRICTION IF ANY:
THIS YR TO CUMUL MONTH DATE ATIVE
- 11. !!OURS IN REPORTING PERIOD 744.00 2184.00 131832.00
- 13. NUMBER OF llOURS REACTOR CRITICAL 637.68 2021.03 87384.47
- 13. REACTOR RESERVE SHUTDOWN HRS
.00
.00 1647.10
- 14. HOURS GENERATOR ON LINE 624.43 1994.21 83708.27
- 15. UNIT RFSERVE SHUTDOWN HOURS
.00
.00
.00
- 16. GROSS TilERMAL ENERGY GEN. (MWH) 1458986.66 4719559.02 181844794.45
- 17. GROSS ELEC. ENERGY GEN. (MWil) 477970.00 15509*.0.00 59634390.00
- 18. NET ELEC. ENERGY GENERATED (MWH) 462818.00 1502915.00 57396245.00
- 19. UNIT SERVICE FACTOR 83.93 91.31 63.50
- 20. UNIT AVAILABILITY FACTOR 83.93 91.31 63.50 al. UNIT CAP. FACTOR (USING MDC NET) 81.10 89.72 55.24
- 22. UNIT CAP. FACTOR (USING DER NET) 75.77 83.82 53.03
- 23. UNIT FORCED OUTAGE RATE 16.07 8.69 15.33
- 34. SilUTDOWNS SCHED. OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACil):
Unit 1 is scheduled to be shutdown approximately 21 days for a periodic terting outage from May 30, 1992 to June 19, 1992. 'Also scheduled is approximately a 4 day outage to search for drywell inleakages. Exact dates at present have not been established.
- 35. IF SliUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START UP:
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST AciiIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1.16 - 9
D IKET NO.
057-C325 UNIT NAME B w -tc= 1 CATE A_***
1992 i
COPPLETED BY do sid # n le TELEPH0aE 919-457-2757 UNIT SHUTDOWNS AND POWER REDUCT1045 REPORT MONTH s'ax5 IM2 l
t METHOD OF LICEMSEE CAUSE & CCRRECTI1rE ACTIO4 TO DURATIO4 SHuiTING DOWN EVEMT SYSTEM CD*PCNEhr PREVENT RECURRENCE NO.
DATE TYPE (1)
(HOURS)
REASON (2)
REACTOR (3)
REPCRT r.3.
CODE (4)
CODE (5)92-011 920229 F
119.51 4
4 1-92-005 TG 94 Reactor scrawed while stop wslwe
- $ee nete testing was in ms. Caused by a defective relay in the Electrohytf-aulle Control System.
t 1:
M 2:
Peason 3:
Method 4:
System Code:
5:
C e t Code F - Forced A-Equipment failure 1-Manual Instructions for Instructions for S - Scheduled (explain) 1-Manual Scram preparation of data entry preparation of data B
Maintenance or test 3-Automatic screm sheets for Lice w Evert eM ry sheets for LER C-Refueling 4-Continuattens Report (LER) file frew file from IEEE Standard t
D-Regulatory 5-Load reductier.s IEEE Standard 805-1983, 803A-1983, per i
restriction 6-Other per MUREG-IC22.
43 REG-1022.Section VI.
[
E-Operator Training &
Section VI. Item 13.b Item 13.c Ltcer.se Exa::Ination F-Adninistrat t we G-Operational error (expl: tn) li -
Other (explain)
- Reactor scramed at 2300 hour0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on Februa7 29.1992, and was syrchronized to the grid at 2334 bcnts on March 5.1992 r
I i
90-0041.MSC Revision 1, September 1991
a -
DOCKET RO.
NO-0325 tJNIT RAME B teswick 1___
CATE art ; 1992
'XP'PLETED BY _sy atd sterie TELEPHONE 919-457-2752 UNIT SHUTIXVIS ARG POWER REDUCTIO 45 REPCRT MOMTH Nerch 1997 MET G Or LICEMSEE CAUSE & CORRECTIVE AC : A TU DURATIDM SHUTTING DOWN EVENT SYSTEM COMP 0fr71T FREVEMT RECURREECE NO.
DATE
. TYPE (1)
(NOURS)
REASON (2)
REACTOR (3)
REPORT NO.
C00E (4)
CODE (5)92-014 920318 F
3
'A 5
m/A X
SC seactor power was reducad to remove IB Reactor Feed Pur@ (RTP) from service due to hunting caused by defective snotor gear unit (MGU). Repaired the MGU.
returned 18 RFP to service and l
increased reactor power to 100%
m thod 4:
Systea Code:
5:
C e t Ccde 1:
Lzs 2:
Reseg; 3:
e F - Forced A-Equipment fatture 1-Manual Instructions for testructions for S - Scheduled (explain) 2-Mam;al Scram preparation of data entry preparation of data B-Maintenance v.- test -
3 --
Automatic scrare s h ts for Licensee Event entry sheets for LER C-Refueling 4-Continuations Report (LER) file from file from IEEE Standar1:
D-Regulatory 5-Lead reductions IEEE Standard 8C5-1963.
803A-1953. per restrictic.,
6-Other per MUREG-1022 NUREG-Ic72.Section VI.
E-Doerator Traireg &
Sectice VI. Item 13.b Item 13.c License Examixtion F-Administrattwe G-Operational errer (erplain)
H-Other (explain)
Revision 1, September 1991 90-0041.MSC L
=.
CP&L CO PLANT PERFORMANCE DAT3 SYSTEM PAGE 2 l RUN DATE 04/03/92 APPENDIX B - AVERAGE DAIL'r POWER LC'JEL RPD39-000 RUN TIME 07:41:25 BRUNSWICK UNIT 2 DOCKET NO. 050-0324 COMPLETED BY RONALD RUMPLE TELEPl!ONE (919)457-2752 MARCH 1992 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 604 17 608 2
604 18 321 3
605 19 448 4
605 20 443 5
605 21 449 6
605 22 449 7
605 23 544 8
606 24 594 9
607 25 596 10 607 26 588 11 606 27 588 12 607 28 588 13 606 29 587 14 605 3C 587.
15 607 31 587 16 607 1.16 - 8' i
_,,.. ~..... ~..,, _ _ _.
CP&L CO PLANT PERFORMANCE DATA SYSTEM PAGE 2
RUN DATE 04/03/92 OPERATING DATA REPORT RPD36-000 RUN TIME 12:38:18 BRUNSWICK UNIT 2 DOCKET NO. 050-0?24 COMPI ETED BY RONALD RUMPLE OPERATING STATUS TELEPHONE (919)457-2752
- 2. UNIT NAME: BRUNSWICK UNIT 1 NOTES - There are 560 f uel bundle!
- 2. REPORTING PERIOD: MARCH 92 in the Reactor Core, 1113 PWR and
- 3. LICENSED THERMAL POWER (MWT): 2436 144 PwR spent fuel bundles in the 4.
NAMEPLATE RATING (GROSS MWE) : 867.O fuel pool, and 0 fuel-bundles in
- 5. DESIGN ELECTRICAL RATING'(NET MWE): 821.0 the new fuel storage vault.
6.
MAX DEPENDABLE CAPACITY (GROSS MWE): 782.0
- 7. MAX DEPENDABLE CAPACITY (NET MWE): 754.0 8.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT, GIVE REASONS:
1 9.
POWER LEVEL TO WHICH RESTRICTED IF ANY (NET MWE): Approximately 600 MWE
- 10. REASONS FOR RESTRICTION IF ANY: Power level restricted to 80% due to EHC problems.
This power level restriction is self-imposed.
THIS YR TO CUMUL MONTH DATE ATIVE
- 11. HOURS IN MPORTING PERIOD 744.00 2184.00 143856.00
- 12. NUMBER OF HOUP.S REACTOR CRITICAL 744.00 1903.35 91616.40
- 13. REACTOR RESERV-' ~*JTDOWN HRS
.00
.00
.00
- 14. HOURS GENERA'. OR OU LINE 744.00 1709.03 86662.52
- 15. UNIT RESERVE S Wr.eOWU HOURS
.00
.00
.00
- 16. GROSS THERMAL ENERGY GEN. (MWH) 1348483.85 3265068.24 183195768.89
- 17. GROSS ELEC. ENERGY GEN. (MWH) 430580.00 1073805.00 69257899.00
- 18. NET ELEC. ENERGY GENLRATED (MWH) 424023.00 1034410.00 56824882.00
- 19. UNIT SERVICE FACTOR 100.00 78.25 60.24
- 20. UNIT AVAILABILITY FACTOR 100.00 78.25 60.24 4
- 22. UNIT CAP. FACTOR (USING DER NET) 69.42 57.69 48.11
- 23. UNIT FORCED OUTAGE RATE
.00 14.38 13.39
- 24. SHUTDOWNS SCHEP. OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Unit 2 is scheduled to be shutdown approximately 30 days for repairs to EHC System, Main Turbine, 2B Reactor Feedpump, ani 4A Feedwater Feater. The outage dates at present are from April 30, 1992 to May 30, 1992.
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START UP:
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 2
INITIAL ELECTRICITY COMMERCIAL OPERATION
).
1.16 - 9
DOCKET NO.
050-0324 LHIT MAME Bruaswick 2 DATE April 1992 COMPLETED BY Ronald Rumo!e TELEPHONE 919-457-2752 UNIT SHUTDOWS AND POWER REDUCil0NS REPORT MONTH March 1992 METHCD OF LICENSEE CAUSE & CORoccTIVE ACTION TO DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT PREVEF RECURRENCE NO.
DATE TYPE (1)
(HOURS)
REA>0N (2)
REC TOR (3)
REPORT NO.
CODE (4)
CCDE (5)92-017 920214 F
0 H
6 N/A TG XC Reactor power being snaintained at approximtely 80% due to continuing electrohydraulic control (EHC) system oscillations. The unit will remain at this power level untti the Unit 2 outage scheduled to start April 30, 1992.
I 1:
hpe
'2.
Ressen 3:
Methor' 4:
Systm Coce:
5:
Cos onent Code F - Forced A-
' Equipment failure 1-Manual Instructions for Instructions for S - Scheduled
'(explain) 2-Manual Scram preparation of data entry preparation of data B-
' Maintenance or test 3-Autometic w ram sheets for Licensee Event entry sheets for LER C-Refueling 4-
' Continuations Report (LER) file from file from IEEE Standard D-Regulatory 5-Load reductions IEEE Standa-:! 805-1983 803A-1983, per restriction.
6-Other ~
per NUREG-1C22 NUREG-1022.Section VI.
E-Operator Training &
Section VI. Item 13.b Item 13.c License Examination F-Adninistrative G-Operational error (explain)
H-Other(explain) 4 90-0041.MSC Revision 1. September 1991
DOCKET NO.
050-0324 UNIT NAME Brunswick 2 DATE Aortl 1992 COMPLETED BY Ronald R en t TELEPHONE 919-457-27S2 W SHUTDOWNS AND POWER REDUCTIONS REPORf MONTH March 1992 METHOD OF LICENSEE CAUSE & CORPICTIVE ACTICN TO DURATION SHUTTING DOWN EVENT SYSTEM COMPONENT PREVENT RECURRENCE NO.
DATE l PYPE (1)
(HOURS)
REASON (2)
REACTOR (3)
REPORT NO.
CODE (4)
CODE (5)92-019 920318 F
0 A
5 N/A IK AC While perfortning primary containment isclation periodic test.' Loth divisions of the hydrogen / oxygen analyzers failed.
Due to the mandated 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,to hot shutdown LCO. power was reduced in preparation for shutdom. One analyzer was repaired and returned to service prior to the LCO expiration; therefore, shutdown was not required. Power increase was further delayed by a failure of the proccss computer and then by a failure of the 2B Reactor Feed j
Pumn motor gear unit. Repairs were completed to the Reacter i
Feed Pianp and power was subsequently restored to 77% due to continuing problses with the Electrohydraulic Control System.
.1:
h 2:
Reason 3:
Nethod.
4:
Syste-Code:
5:
Corcerient Code F - Forced A-Equipment failure 1-Manual Instructions for Instructions for 1,
G - Scheduled (explain) 2-Manual Scram preparation of data entry preparation of data B-Maintenance or test 3-Automatic scram sheets for Licensee Event entry sheets for LER C-Refueling 4-Continuations Report (LER) file from file from IEEE Standard D-Regulatory 5-Load reductions IEEE Standard 805-1983 803A-1983, per restriction S-Other per MUREG-1022.
NUREG-1022. Section TI.
Sect on VI. Item 13.b Item 13.c E-Operator Training &-
i License Examination F-Adninistrative G-Operational error (explain) ji - -
Other(explain) 90-0041.MSC Revision 1, September 1991