ML20094K024
| ML20094K024 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/29/1992 |
| From: | Rumple R, Spencer J CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9203170346 | |
| Download: ML20094K024 (7) | |
Text
.
o CP&L i,arolina Power & Light Comparty Ur2G7AmanWL%tetwrtzifac2 Brunswick Nuclent Project P, O. Box 10429 Southpol:t, NC 28461-0429
- l.t ; 10 T332 FILE
B09-135100 U.S. Nuclear Regulatory Conunission Washington, DC 20555 Attn:
Document Control Desk BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50 324 LICENSE NOS. DPR-71 AND DPR-67 MONTHLY OPERATING REPORT Gentlemen:
In accordarce with Technical Specification 6.9.1.11 for the Brunswick Steam Electric Plant, Units 1 and 2, Carolina Power & Light Company herewith submits the report of operating statistics and shutdown experience for the month of February 1992.
Very truly yours, n
b' W* Ns ?
/ t J. W. Spencer, General Manager Brunswick Nuclear Project RDR/jlh 90 '041.MSC Enclosures cc:
Ms. D. M. Aslett Mr. T. C. Bell Mr. R. M. Coats Mr. S. D. Ebneter Ms. R. S. Gatewood Mr. M. D. Mill Mr. N. B. Le Mr. W. R. Murray Mr. R. G. Oehl Mr. R. L. Prevatte Mr. R. P. Starkey
[
Mr. F. Yost 7
f Y INPO pfNo 1CuOUJ 9203170346 920229 PDR ADOCK 05000324 R
.CP&L'CO PLANT PERFORMANCE DATA SYSTEM PAGE 1
RUN DATE 03/06/92 APPENDIX B - AVERAGE DAILY POWER LEVEL RPD39-000 RUN TIME, 12:18:10 BRUNSWICK Ut1IT 1 DOCKET NO. 050-0325 COMPLETED BY RONALD RUMPLE TELEPHOllE (919)457-2752 FEBRUARY 1992 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 779 37 775 2
755 (8
775 3
579 19 775 4
285 20 776 5
775 21 776 6
777 22 775 7
776 23 775 8
776 24 775 9
775 25 776 10 777 26 774 11 777 27 775 12 776 28 775 13 776 29 737 14 775
~
15 775 16 774 1.16 - 8
CP&L'CO PLANT PERFORMANCE DATA SYSTEM PAGE 1
-RUN DATE 03/06/92 OPERATING DATA REPORT RPD36-000 l
RUN TIME-12:18:11 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 2.
REPORTING PERIOD: FEBRUARY 92 bundles in the Reactor core, 1090 3.
LICENSED THERMAL POWER (MWT): 2436 nwu and 160 PWR spent fuel bundles
- 4. NAMEPLATE RATING (GROSS MWE): 867.0 in the fuci pool, and 0 fuel 5.
DESIGN ELECTRICAL RATING (NET MWE) : 821.0 bundles in the new fuel storage
- 6. MAX DEPENDABLE CAPACITY (GROSS MWE) : 791.0 vault.
- 7. MAX DEPENDABLE CAPACITY (NET MWE): 767.0 8.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT, GIVE REASONS:
9.
POWER LEVEL TO WHICH RESTRICTED IF ANY (NET MWE):
- 10. REASONS FOR RESTRICTION IF ANY:
THIS YR TO CUMUL MONTH DATE ATIVE
- 11. HOURS IN REPORTING PERIOD 696.00 1440.00 131088.00
- 12. NUMBER OF HOURS REACTOR CRITICAL 695.00 1383.35 86746.79
- 13. REACTOR RESERVE SHUTDOWN HRS
.CO
.00 1647.10
- 14. HOURS GENERATOR ON LINE 695.00 1369.78 83083.84
- 15. UNIT RESERVE-SHUTDOWN HOURS
.00
.00
.00
- 16. GROSS-THERMAL-ENERGY GEN. (MWH) 1641131.25 3260572.36 180385807.79
- 17. GROSS ELEC.--ENERGY GEN. (MWH) 538145.00 1072940.00 59156420.00
- 18. NET ELEC. ENERGY GENERATED (MWH) 521783.00 1040097.00 56933427.00
- 19. UNIT SERVICE FACTOR-99.86-95.12 63.38
-20. UNIT AVAILABILITY FACTOR 99.86 95.12 63.38
55.10
- 22. UNIT CAP. FACTOR (USING DER NET) 91.31 87.98 52.90'
- 23. UNIT FORCED OUTAGE RATE
.14 4.87 15,33
- 24. SHUTDOWNS-SCHED.-OVER NEXT.6 MONTHS (TYPE,-DATE, AND DURATION OF EACH):
Unit 1 is scheduled to be shutdown approximately 21 days in May for a periodic testing outage. The outage dates at present have not been established.
- 25. IF SHUTDOWN AT-END OF REPORT PERIOD, ESTIMATED DATE OF START UP: 3/6/92
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED
-INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1.16 - 9 i
l-l l
L
. ~
4 4
I 00CKET NO.
050-0325 UNIT NAME Brteswi:K1 0 ATE' Ma % 1992 COMPLETED BY
'onald R n ie TELEPHONE 919-457-2752 l
tt41T SHUTD0VNS AND POWER REDUCTIONS REPORT MONTH February 1992 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO DURA 110N SHUTTING DOWN EVENT CODE (4)
CODE (5)
PREVENT RECURRENCE NO.
DATE TYPE (1)
(HOURS)
REASON (2)
REACTOR (3)
REPGQT NO.
i 92-001 920203 F
0 A
5 N/A SJ SPT Reactor power was reduced to isolate 1-3B feedwater heater (FWH). Failed bolts were fo M on the heater head structural support. Root cause was found to be a lack of lateral suoports on the extraction steam ciping to this FW.92-011 920229 F
1.00 A
3 1-92-005 N/A N/A Reactor scrawed while cortrol valve i
To be To be testing was in progress.
incluced included Investigation is underway to in next in next determine the cause.
l report report 1:
Tyre 2:
Reason 3:
Method 4:
System Code:
5:
C m ent Code j
F - Forced A-Equiprer:t failure 1-Manual Instructions for Instructions for i
S - Sche 1uled (explain) 2-Manual Scram preparation of data entry preparation of data I
B-Maintenance or test 3-Automatic scram sheets for Licensee Event entry sheets for LER i
C-Refueling 4-Continuations Report (LER) file from file from IEEE Standard i
D-Regulatory 5-Load reductions IEEE Standard 805-1983.
603A-1983, per i
restriction 5-Other per NUREG-1022.
E-Operator Training &
Section VI, Item 13.b Item 13.c License Examination i
F-A tinistrative G-Operational error (explain) i H-'
Other (explain)
l,'
~
CP&L'CO PLA~..T PERFORMhNCE DATA SYSTEM PAGE 2
RUN DATE 03/06/9?
APPENDIX B - AVERAGE DAILY POWER LEVEL RPD39-000 RUN TIME, 12:18:10 BRUNSWICK UNIT 2 DOCKET No. 050-0324 COMPLETED BY RONALD RUMPLE TELEPHONE (919)457-2752 FEBRUARY 1992 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 686 17 644 2
130 18 645 3
-14 19 646 4
-13 20 637 5
-12 21 613 6
-12 22 601 7
-14 23 605 8
-13 24 605 9
-13 25 604 10
-13 26 604 11
-13 27 604 12
-13 28 604 13
-14 29 603 14 386 15 634 16 644 1.16 - 8
~
CP6L CO PLANT PERFORMANCE DATA SYSTEM PAGE 2
- RUN.DATE 03/06/92 OPERATING DATA REPORT RPD36-000 RUN TIME 16
- 06:37 BRUNSWICK UNIT 2 DOCKET NO. 050-0324 COMPLETED BY RONALD RUMPLE OPERATING STATUS TELEPHONE (919)457-2752
--1.: UNIT NAME: BRUNSWICK UNIT 2 NOTES -There arn %0 f ucl hund1co 2.
REPORTING PERIOD: FEBRUARY 92 in the Peacter core, 1113 PMR and 3._-LICENSED THERMAL POWER (MWT): 2436 144 PvP spent fuel bundlem in the
- 4. NAMEPLATE RATING (GROSS MWE) : 867.O fuel pool, and 0 fcol bundlen in 5.
DESIGN ELECTRICAL RATING (NET MWE) : 821.0 the new fuel storage vault.
- 6. MAX DEPENDABLE CAPACITY (GROSS MWE) : 78 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:
- 9. POWER LEVEL TO WHICH RESTRICTED IF ANY (NET MWE):
- 10. REASONS FOR RESTRICTION IF ANY:
THIS YR TO CUMUL MONTH DATE ATIVE
~11. HOURS IN REPORTING PERIOD 696.00 1440,00 143112.00
-13. NUMBER OF HOURS REACTOR CRITICAL 493.16 1159.35 90872.40
- 13. REACTOR RESERVE SHUTDOWN HRS
.00
.00
.00
- 14. HOURS GENERATOR ON LINE 408.92 965.03 85918.52
- 15. UNIT RESERVE SHUTDOWN HOURS
.00
.00
.00 ifa. GROSS THERMAL ENERGY GEN. (MWH) 780272.24 1916584.39 181847285.04-
- 17. GROSS ELEC. ENERGY GEN. (MWH) 269810.00 635225.00 58819319.00 18.- NET-ELEC. ENERGY GENERATED (MWH)-
248391.00 610387.00 56400859.00
- 19. UNIT SERVICE FACTOR 58.~5 67.02 60.04
- 20. UNIT-' AVAILABILITY. FACTOR 58,75 67.02 60.04
- 23. UNIT CAP. FACTOR--(USING DER NET) 43.47 51.63 48.00.
- 23. UNIT FORCED-OUTAGE' RATE 11.25 22.93 13.49
- 24. SHUTDOWNS SCHED. OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Unit 2 in scheduled to be shutdown approxir.ately 21 days beginning in Parch for repairs to the EHC Systen, Main Turbine, and 2B Reactor Feedpump.
The outage datec at present havo not been entablished.
- 35. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATF OF START UP:
- 26. UNITS _IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED
' INITIAL. CRITICALITY t '
INITIAL ELECTRICITY COMMERCIAL OPERATION 1.16 - 9 l
i I
l
.__...n e
- 4 I
DOCKET NO.
050-0324 UNIT NAME Brunswick 2 DATE merth 1992 C0"PLETED BY _ Recaid 2: role TELEPHONE 919-457-2752 UNIT S W TD0VNS AND POWER REDUCTIONS REPOR? t10 NTH February 1992 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO DURATION SHUTTING DOVN EVENT CODE (4)
CODE (5)
PREVENT RECT 9EENCE 40.
DATE TYPE (1)
(HOURS)
REASON (2)
REACTOR (3)
REPORT NO.92-015 920202 F
287.08 A
3 2-92-001 TG ACC Reactor scremed during control valve testing due to Electrchydraulic Contro? (EHC)
System failure. Susr=cted cause was air or nitrogen in the system caused by accumulator perfomance or venting. Repairs were performed on EHC and startup was comenced,
[
However, the reactor was shut down before synchmizing to the grid due to repairs needed en 28 reactor feed pump. Repairs were completed but I
startup was prevented due to seismic evaluation needed on Foxboro cabinets. After evaluation was coreleted, the unit was started up on 2/14/92 and syechronized to the 1
grid.
I:
Tyrg 2:
Reasco 3:
"et md 4:
System Cece:
5:
C m eat Code F - Forced A-Equipment failure 1-Manual Instructicas fer Instructions for 5 - Scheduled (exple'n) 2-Manual Scram preparatien of data entry preparation of data B-Maintecance or test 3-Automatic scran 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 restr tion 6-Other per MUREG-1022.
E-Opern or Trainirg &
Section VI. Item 13.b Item 13.c License Examinetien F-Achini strative G-Operetieral error (explain)
H-Other (explain]
90-0041.MSC
_ _ _ _ _