ML20085H834
ML20085H834 | |
Person / Time | |
---|---|
Site: | Catawba |
Issue date: | 05/31/1995 |
From: | Robert Williams DUKE POWER CO. |
To: | |
Shared Package | |
ML20085H400 | List: |
References | |
NUDOCS 9506210320 | |
Download: ML20085H834 (11) | |
Text
._ - - - . - - - - - - _ .- - - _ _ _ _ - - _ _ _ _ . - - . . .
i j .. ,
i OPERATING DATA REr0RT t
i DOCKET NO 50-414
! DATE June 15. 1995
.0PERATING STATUS COMPLETED BY R.A. Willians TELEPHONE 704-382-5346
- 1. Unit Nase: Catawba 2
- 2. Reporting Period: May 1, 19?5-May 31, 1995
- 3. Licensed Thersal Foser (Mt): 3411
- 4. Naseplate Rating (Gross Wel 1305e Notes 'eNaseplate Rating
- 5. Design Electrical Rating (Net Me): 1145 (Bross W e) calculated as C. Maxinus Dependable Capacity (Bross Me): 1192 1450.000 MVA : .90 power l 7. Maxinus Dependable Capacity (Net We): 1129 .
factor per Page 111,
- 8. If Changes occur in Capacity Ratings (Itess Number 3 Through 7) Since Last NURE6-0020.
Report. Give Reasons:
- 9. Power Level To Which Restricted, if Any (Net Me)
j 10. Reason for Restrictions, If any:
This Month Yr.-to-Date Cusulative
- 11. Hours In Reporting Feriod 744.0- 3623.0. 76992.0
- 12. Number Of Hours Reactor Was Critical 709.0 3286.6 60295.9
- 13. Reactor Reserve Shutdeun Hours - '
- - 14. Hours 6ererator On-Line 606.2 3245.4 59306.9
- 15. Unit Reserve Shutdown Hours --0-- --0-- -
16.BrossThersalEnergyGenerated(MWH) .2291911 10959113. 190657996
- 17. Gross Electrical Energy Generated (MH) 808548 3888063 67527443
- 18. Het Electrical Energy Benerated ( MH) 764871 3676619 63642172
- 19. Unit Service factor 92.2 89.6 77.0
- 20. Unit Availability Factor 92.2 89.6 77.0
- 21. L' nit Capacity Factor (Using MDC Net) 91.1 89.9 73.1
- 22. Unit Capacity Factor (Using DER Net) 89.8 88.6 72.2
, 23. Unit Forced Dutage Rate 7.8 10.4 8.9
- 24. Shutdown Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling - October 06, 1995 - 39 days
- 25. If Shut Down At End Of Repert Period. Estinated Date of Startup:
26.UnitsIr.TestStatus(PriortoCoseercialOperation): Forecast Achieved INITIALCRITICALITY i
INITIAL ELECTRICITY COMERCIAL CPERATION l
, 9506210320 950615 t PDR ADOCK 05000413
- l. R PDR
QPERAilNS DATA REPORT l
l DOCKET NO 50-414 UNIT Catamba 2 DATE June 15. 1995 l COMPLETED BY P.A. Willians l TELEPHONE 704-382-5346 l
l MONTH May. 1995 Qal AVERASE DAILY POWER LEVEL p11 AVERA6E DAILY POWER LEVEL (MWe-Net) (MWe-Net)
- I 0 17 !!29 2 0 la 1131 3 179 19 1134 4 1089 20 1145 5 1143 21 1142 6 1147 22 1135 _
7 1146 23 !!33 8 1139 24 !!32 l
9 !!39 25 !!29 I l
10 1132 26 1129 l 11 1135 27 1130 12 1141 28 1140 13 1139 29 1136 14 1136 30 1139 15 1133 31 1144 16 1137
~.
4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-414 -
UNIT NAME carawasa z ,
DATE ue/lo/vp _
REPORT MONTH May 1995 COMPLETED BY x. A. williams TELEPHONE (/uej-Juz-oJee l- (1) 2) (4) (5) ,
E HOD T A OF LICENSE N Y S SHUT EVENT SYS- CAUSE AND CORRECTIVE O P DURATION O DOWN REPORT TEM COMPONENT ACTION TO
, . DATE E HOURS N R/X NO. CODE CODE PREVENT RECURRENCE ,
4 95-'5- 1 F 14.95 A --
CH HTEXCH REACTOR TRIP DUE TO LO ID STEAM GENERATOR FEEDWATER' LEVEL 5 95 1 F 42.85 A 3 HH PUMPXX IDSS OF FEEDWATER PUMP FLOW 3-P 95 3 F --
A --
HH VALVEX LO FEEDWATER ISOLATION VALVE TEMPERATURE ;
1 1
T 1
(2 (3)Method: (4)
(1hForced eason-1-Manual Exhibit G - Instructions for Preparation of Data
' i.
S Scheduled A-Egyipment FailureB-Maintenance or test (Explain) ~2-Manual Scram Ent y Sneets For Licensee !
C-Refueling 3-Automatic Scram 4-Other (Explain)
Event Report (LER File ( N G-0161))
l D-Regulato n Restriction , ,
E-Operator Training & License Examination >
F-Administrative (5)' I G-OkeratorErr9r-(Explain) Exhibit I - Same Source
- H-O her (Explain) t u
f 6
. . _ _ _ _ _ . _ _ _ . _m_____ -_ .__. _ _ _ _ _ _ __++_e- _ _ _ 6 e- -r- - -evi- _ we -e. -_ _ . _ __ -_______________.-_.______._._.m..__.- -
a ,
- d d
DOCKET: 50-414 4
UNIT: Catawba 2 Date: 06/15/95 NARRATIVE
SUMMARY
MONTH: May 1995 Catawba Unit 2 began the month of May in an. outage due to lo-lo '2B' steam generator feedwater level. The unit was placed on-line 05/01/95 at 1457. At 14% power the unit experienced a reactor trip due to loss of feedwater flow at 1603. The unit was placed on-line on 05/03/95 at 1054. During power escalation, the unit held at 20%
power from 1200 to 1550 due to lo feedwater isolation valve temperature. The unit returned to 100% full power on 05/04/95 at 1344 and operated at or near 100% full power the remainder of the month.
Prepared by: R. A. Williams Telephone: (704)-382-5346
I l
. i I
MONTHLY REFUELING INFORMATION REQUEST
- 1. Facility name: Catawba. Unit 2
- 2. Scheduled next refueling shutdown: October 1995
- 3. Scheduled restart following refueling: November 1995 THE PROJECT MANAGER HAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S. CHANGE OR LICENSE AMENDMENT. THEREFORE, QUESTIONS 4.
THROUGH 6 WILL NO LONGER BE MAINTAINED IN THIS REPORT. I
- 4. Will refueling or resumption of operation thereafter require a I technical specification change or other. licence amendment? i i
If yes, what will these be?
If no, has reload design and core configuration been reviewed by I Safety Review Committee regarding.unreviewed safety questions? )
- 5. Scheduled date(s) for submitting proposed licensing action and I supporting information.
- 6. Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
- 7. Number of Fuel assemblies (a) in the core: 121 J (b) in the spent fuel pools AA1 '
- 8. Present licensed fuel pool capacity: 1418 Size of requested or planned increase: --- j
- 9. Projected date of last refueling which can be accommodated by present licensed capacity: September 2011 DUKE POWER COMPANY DATE: June 15. 1995 Name of
Contact:
R. A. Williams Phone: .1104)-382-5346
l l
OPERATINS DATA REPORT DOCKET NO 5 H 13 DATE June 15. 1995 OPERATING STATUS COMPLETED BY R.A. Williaes I' i
TELEPHONE 704-382-5346 l 1. Unit Nase: Catawba 1 !
- 2. Reporting Period: May 1, 1995-May 31, 1995 I
- 3. Licensed Thernal Pcuer (MWt): 3411 l
- 0. Naseplate Rating (Gross MWe): 1305e Notes INaseplate Rating =~] )
l l
S. Design Electrical Rating (Net MWe): 1145 (6ross MWel calculated as
- 6. Maximaa Dependable Capacity (Gross MWe): 1192 1450.000 MVA x .90 pr;mer
- 7. Maxieus Dependable Capacity (Net MWe): 1129 factor per Page 111,
- 8. If Changes Occur in Capacity Ratings (!!eas Nutbar 3 Through 7) Since Last NUREG-0020. !
Peport. Give Reasons:
i
- 9. Power Level To Which Restricted, If Any (Net MWe): l
- 10. Reason Fcr Restrictions, If any: l This Month Yr.-to-Date Cuaulative
- 11. Hours In Reparting Period 744.0 3623.0 86976.0
- 12. Number Of Hours Reacter Was Critical 744.0 2671.3 67182.9
- 13. Reacter Reserve Shatdown Hours ~0-- --0-- --0--
- 14. Hours Generator On-Line 726.8 2576.2 65951.7
- 15. Unit Reserve Shutdown Hours --0-- - --0--
- 16. Gross Thersal Energy Generated (MWH) 2309885 8435817 214579248
- 17. Gross Electrical Energy Generated (MWH) 815298 3009723 75693473
- 18. Net Electrical Energy Generated (MWH) 769606 2837090 71160552
- 19. Unit Service Factor 97.? 71.1 75.8
- 20. Unit Availability Facter 97.7 71.1 75.0
- 21. Unit Capacity Factor (Using MDC Net) 91.6 69.4 72.2
- 22. Unit Capacity Factor (Using DER Net) 90.3 68.4 71.5 j
- 23. Unit Forced Outage Rate 2.3 1.6 8.8
- 26. Shutdown Scheduled Over Next 6 Months (Type, Date, and Dcration of Each):
None
- 25. If S>tt Down At End Of Report Period. Estisated Date of Startup:
- 26. UniL in Test Status (Prior to Coenercial Operation): Forecast Achieved INITIAL CR1TICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
'*P
4 4
i~
OPERATINE DATA REPURT j I
DOCKET NO _ 50-413 q lmIT ' Catasha 1 ; j i' ; . DATE June 15. 1995- q C0lFLETED H - R.A. Williams !
' TELEPH8ME 704-382-5346 )
2 !
-l MONTH _ M a . 1995 , -
j i
AytuneE DAILY POWER LEVEL 1
. M1. A DA1 AVERAGE DA!LY PDHER LEVEL :
(HWe-Net) (MWe-Net) i
- 1. 1153 17 ' 1141 1
2 1155 18 1142 ~1 3 !!61 19 - 1144 j l
4 1158- - 20 1124 ,
l 5 1155 21 1152 6 1159 22 1150-7 1158 23 812 8 1156 24 456
- 9 !!52 25 456 10 1]iB 26 81 11 1149 27' 386 i 1
12 1153 2B 1130 I 13 1152 29 !!41 14 1149 30 1142 ,
15 1145 31 1149-16 1150 ;
4
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- 9 E"'~'W f 7'
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-413 UNIT NAME cATAWHA 1 DATE 06/1o/93 _
REPORT MONTH May 1995 COMPLETED BY x. A. w1111ams PAGE 1 OF 2 TELEPHONE (Ju4)-Juz-3346 (1) (2 (3) (4) (5)
R)
E MET-HOD T A OF LICENSE N Y S SHUT EVENT SYS- CAUSE AND CORRECTIVE O P DURATION O DOWN REPORT TEM COMPONENT ACTION TO
. DATE E HOURS N R/X NO. CODE CODE PREVENT RECURRENCE 8-P 95- 5-23 F --
B --
CB PUMPXX REACTOR COOLANT PUMP SEAL WATER RETURN HEAT EXCHANGER MAINTENANCE 9-P 95- 5-26 F --
A --
CB .PUMPXX '1A' REACTOR COOLANT PUMP UPPER MOTOR OIL LEVEL ALARM 4 95- 5-26 F 17.22 A --
CB PUMPXX '1A' REACTOR COOLANT PUMP UPPER MOTOR BEARING SITE GLASS VENT LINE 10-P 95- 5-27 F --
F --
HG XXXXXX SECONDARY CHEMISTRY OUT OF SPEC 11-P 95- 5-27 F --
H --
IE INSTRU EVALUATION OF EXCORE NUCLEAR INSTRUMENTATION SYSTEM POWER TILT RATIO (1) (2)Reason (3)Nethod: (4)
F Forced
- Exhibit G - Instructions S Scheduled 1-Manual for Preparation of, Data A-Equipment FailureB-Maintenance or test (Explain) 2-Manual Scram EntW Sneets For Licensee C-Refueling 3-Automatic Scram (LER D-Regulatory Restriction 4-Other (Explain) Event File Report (NUREG-0161))
E-Operator Training & License Examination F-Administrative (5) i G-Operator Error (Explain) Exhibit I - Same Source H-Other (Explain) l
. ___________- _ _ _ _. - _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ _ ~__
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-413 '
UNIT NAME CATAWBA 1 DATE u b/1:>/ v d .
REPORT MONTH May 1995 COMPLETED BY M. A. williams PAGE 2 OF 2 TELEPHONE t/ue)-Juz-d346 (1)
{2) g (4) (5)
E HOD T A OF LICENSE N Y S SHUT EVENT SYS- CAUSE AND CORRECTIVE O P DURATION O DOWN REPORT TEM COMPONENT ACTION TO o DATE E HOURS N R/X NO. CODE CODE PREVENT RECURRENCE 12-P 95- 5-27 F --
B --
IA INSTRU ADJUSTMENT OF NUCLEAR INSTRUMENTATION SYSTEM / THERMAL POWER MISMATCH (1)F Forced (2)Reason- (3)Method: (4)
Exhibit G - Instructions S Scheduled A-Equihment FailureB-Maintenance or test (Explain) 1-Manual for Preparation of Data 2-Manual Scram Ent W Sneets For Licensee C-Refueling 3-Automatic Scram Event Report (LER D-Regulatory Restriction , ,
4-Other (Explain) File (NUEG-0161))
E-Operator Training E License Examination F-Administrative (5)
G-Operator Err 9r (Explain) Exhibit I - Same Source H-Other (Explain)
__.--._-____ - - -__ _-_.__.-._ _ -_____ - - _ - _ r - , - - _ - _ _ . _ - . _ _ _ .
l i
\
DOCKET: 50-413 UNIT: Catawba 1 Date: 06/15/95 l
NARRATIVE
SUMMARY
l MONTH: May 1995 l
Catawba Unit 1 began the month of May operating at 100% full power..On 05/23/95 at 0841 the unit began decreasing power to investigate a suspected reactor coolant pump seal water return heat exchanger. leak. Ac 1530 the unit held at 45% power until 05/26/95 at 0138 due to reactor coolant pump seal water return heat exchanger maintenance. The unit reduced to 18% power and held from 0440 to 1303 due to '1A' reactor coolant pump upper motor oil level alarm. The unit was taken off-line on 05/26/95 at 1432 due to '1A' reactor coolant pump upper motor bearing site glass vent line replacement (reactor remained critical). The unit returned to service on
~
05/27/95 at 0745. During power escalation, the unit held at 30% power from 1019-to 1150 due to secondary chemistry out of spec. The unit held at 45% power from 1335 to 1351 to evaluate excore nuclear instrumentation system power _ tilt ratio. At 65%
power the unit held from 1500 to 1645 due to adjustment of nuclear instrumentation system / thermal power mismatch. The unit returned to 100% full power on 05/28/95 at 0130 and operated at or near 100% full power the remainder of the month.
Prepared by: R. A. Williams Telephone: (704)-382-5346
MONTHLY REFUELING INFORMATION REOUEST
- 1. Facility name catawba. Unit i
- 2. Scheduled next refueling shutdown: June 1996 1
- 3. Scheduled restart following refueling: Seotember 1996 THE PROJECT MANAGER HAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S. CHANGE OR LICENSE AMENDMENT. THEREFORE, QUESTIONS 4 THROUGH 6 WILL NO LONGER BE MAINTAINED IN THIS REPORT.
- 4. Will refueling or resumption of operation thereafter require a technical specification change or other licence amendment?
If yes, what will these be?
If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?
- 5. Scheduled date(s) for submitting proposed licensing action and supporting information.
- 6. Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
- 7. Number of Fuel assemblies (a) in the core: 132 (b) in the spent fuel pool: EEn
- 8. Present licensed fuel pool capacity: 1418 Size of requested or planned increase: ---
- 9. Projected date of last refueling which can be accommodated by present licensed capacity: September 2009 DUKE POWER COMPANY DATE: June 15. 1995 Name of
Contact:
R. A. Williamn Phone: (7041-382-5346