ML20214G131
| ML20214G131 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/30/1987 |
| From: | Reavis J, Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8705260428 | |
| Download: ML20214G131 (15) | |
Text
i OPERATINSDATAREPORT DOCirET 50-413 DATE 5-15-87 OFERATINS STAitS COMPLETED PY J. A. Peavis
...... =
TELEPHONE 704/373-7567
- 1. Unit Nase: CATAWBA 1
- 2. Reporting Period: APRIL 1, 1987-APRIL 30, 1987
'3. Licensed Thermal Power (MWt):
3411
- 4. haseplate Rating (Gross MWe):
1305 i Notes *Naseplate Rating I
- 5. Design Electrical Rating (Net MWe):
!!45 I (Gross MWel calculated as 1
- 6. Maxisus Dependable Capacity (6ross MWe):
I 1450.000 MVA x.90 power i
- 7. Mailsus Dependable Capacity (Net MWe):
!!45 i factor per Page lii, I
- 8. If Changes Occur in Capacity Ratirgs (Itess Nusber 3 Through 7) Since Last i NURE6-0020.
I Report. 61ye Reasons:
I,
.........I
- 9. Power Level To Which Restricted, If Any (Nat MWe):
- 10. Reason For Restricttons, If anya _....,_...........................
This Month Yr.-to-Date Cuaalative
!!. Hours In Reparting Period 719.0 2,879.0 16,104.0
- 12. Naater Of Hours Reactor Was Critical 706.1 2,522.1 11,559.5
- 13. Reactor Reserve Shutdown Hours
--0--
- --0--
- 14. Hours Generator On-Line 702.6 2,466.7 11,137.4
- 15. Unit Reserve Shutdoun Hours
--0--
--0--
--0--
- 16. Gross Thereal Energy Generated (MWH) 2,343,400 8,039,904 34,612,126
- 17. Gross Elect-ical Energy Generated (MWH) 821,480 2,831,900 12,112,632
- 18. Net Electrical Energy Generated (MWH) 777,460 2,664,610
!!,287,616
- 19. Unit Service Factor 97.7 85.7 69.2
- 20. Unit Availability Factor 97.7 85.7 69.2
- 21. Unit Capacity Factor (Using MDC Net) 94.4 80.8 61.2
- 22. Unit Capacity Factor (Using DER Net) 94.4 80.8 61.2
- 23. Unit Forced Outage Rate 2.3 14.3 18.7
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
.......W n.9...................
- 25. If Shut Down At Erd Of Report Period. Estisated Date of Startups,.....................................................,
- 26. Units In Test Status (Prior to Consercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMERCIAL OPERAi!0N 8705260428 B70430 1
4 PDR ADOCK 05000413 R
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-413 UNIT Catasha !
DATE May 15,1987 CDPfLETED BY J. A. Feavis TELEPHONE 704-373-7567 MONTH APRIL,1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)
(MWE-Net) i 1144 17 1139 2
1141 18
!!25 3
1139 19 1014 4
1141 20 1009 5
1143 21 1120 6
!!35 22 1132 7
1137 23
!!29 8
1137 24 1129 9
467 25 1136 10 497 26 1135 11 1092 27 1136 12 1120 28 1135
/
13 1135 29 1137 14
!!37 30 1130 15 1132 16 1138 I
1
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f UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-413 j
UNI T NAME _CATAL_JB A_1__ ______
Pag 2 1 of 2
___Ap_t l_1987_
COMPLETED hE L
R hE[h REPORT MONTH i
TELEPHONE _17041:323:2g^7 _
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i 24-p i 87 6 ir jB i -- i i CF l VALVEX i INSERVICE TEST SURVEILLANCE FOR
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F Forced Reason:
Method:
Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of' Data B-Maintenance or test 2-Manual Scram Entry Sheets For Licenses C-Refueling 3-Automatic Scram Event Report (LER)
D-Regulatory Restriction 4-Other (Explain)
File (NUREG-0161)
E-Operator Training & License Examination F-Administrative (5)
G-Operator Error (Explain)
Exhibit I - Same Source j H-Other (Explain)
UNIT SKUTDOWNS AND POWER REDUCTIONS DOCKET NO.__5Q-413_________'__
UNIT NAME CATAWBA 1 Page 2 cf 2 DATE 05/15/87 REPORT MONTH _______AEC l_1987_
COMPLETED BY _GERALQ_REAVIS____
i TELEPHONE _17Qt i-373--7567_ _ _
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(1)
(2)
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F Forced Reason:
Method:
Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram Entry Sheets For Licensee l C-Refueling 3-Automatic Scram Event Report (LER)
D-Regulatory Restriction 4-Other (Explain)
File (NUREG-OI61)
E-Cperator Training & License Examination F-Administrative (5)
G-Operator Error (Explain)
Exhibit I - Same Source H-Other (Explain)
I 1
m DOCKET NO:
50-413 UNIT:
Catawba 1.
DATE:
5/15/87 NARRATIVE
SUMMARY
t Month:' Apr11, 1987 Catawba Unit 1 began the month at 100% power. On 4/09 at 1041, the unit tripped after a feedwater regulating valve failed closed. The unit was returned to 2
service on 04/10 at 0310 and increased power to 100%.
It remained at that level for the rest of the month.
f 1'
1 4
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MONTRLY REFUELING INFORMATION REQUEST F
-1.
Facility names Catawba Unit 1 2.
Scheduled next refueling shutdown: October, 1987 3.
Scheduled restart following refueling: December, 1987-4.
Will refueltag or resumption of operation thereafter require a technical specification change or other license amendment? Yes i.
If yes, what will these be? Technical Specification Revision If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A 5.
Scheduled date(s) for submitting proposed licensing action and es.pporting information N/A 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 193 (b) in the spent fuel pool 64 8.
Present licensed fuel pool capacity: 1418 Size of requested or planned increases 9.
Projected date of last refueling which can be accommodated by present licensed capacity: September, 2011 DUKE POWER COMPANY DATE: May 15, 1987 Name of
Contact:
'J. A. Reavis Phones 704-373-7567
OPERATIN6 DATA REPORT DOCKET 50-414 DATE 5-15-87 OPEFATING STATUS COMPLETED BY J. A. Reavis TELEPHONE 704/373-7567
- 1. Unit Naee: CATAb8A 2
- 2. Reporting Period: APRIL 1, 1987-APRIL 30, 1987'
- 3. Licensed Thereal Power (Mt):
3411
- 4. Naseplate Rating (6ross Mel:
1305 i Notes *Naseplate Rating I
- 5. Design Electrical Rating (Net Me):
1145 I (6 toss Me) calculated as 1
- 6. Manteue Dependable Capacity (6ross Mel:
1 1450.000 MA x.90 power i
- 7. Maileus Dependable Capacity (Net Me):
1145 i factor per Page lit, I
- 8. If Changes Occur in capacity Ratings (Itees Nueber 3 Through 7) Since Last i NUREG-0020.
I Report. Give Reasons:,_ _,_ _,,,,,_ _,,
I,__________
l 90 Power Level To Which Restricted, If Any (Net Me):
- 10. Reason For Restritttons, If anya,,,,,,,,,,,,_, _,,,,,,,,,, _ _ _,,,,,,,,,,,,,_,,_,,,,_,_,,,,,,,,,,,,,,,_,,_ _
This Month Yr.-to-Date Cueulative
- 11. Hours In Reporting Period 719.0 2,879.0 6,120.0
- 12. Number Of Hours Reactor Was Critical 525.9 2,361.4 3,754.2
- 13. Reactor Reserve Shutdown Hours
--0-- -
--0--
- 14. Hours 6ererater On-Line 482.5 2,267.1 3,592.8
- 15. Unit Reserve Shutdown Hours
--0--
--0--
--0 ~
. 16.GrossTherealEnergyGenerated(MH) 1,500,570 7,234,564 11,279,178
- 17. Gross Electrical Energy Generated ( WHI 521,565 2,523,784 3,946,926
- 18. Net Electrical Energy 6enerated ( MH) 483,962 2,363,646 3,660,848 19.UnitServiceFactor 67.1 78.7 58.7
- 20. Unit Availability Factor 67.1 78.7 58.7
- 21. Unit Capacity Factor (Using M9C Net) 58.8 71.7 52.2
- 22. Unit Capacity Factor (Using DER Net) 58.8 71.7 52.2
- 23. Unit Forced Outage Rate 32.9 19.3 40.6
- 24. Shutdowns Scheduled Over Mont 6 Months (Type, Date, and Duration of Each):
......Honc...........................................................................-......--
- 25. If Shut Down At End Of Report Period. Estlested Date of Startups.,,,,,,,,,,,,,,,,,,,,,,,,, _.........................
2t.. Ur.itt in Test Status (Prior to Coseercial Operation):
Forecast Achieved INii!ALCRITICAlliY INITIALELECTRICliY COMMERCIAL QPERATION w-______._---_-_-____._-__..
tr :
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AVERAGE DAILY UNIT POWER LEVEL.
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DOCKET NO.
50-414 UNIT Catawba 2 DATE -May 15, 1987 COMPLETED BY J. A. Reavis TELEPHONE 704-373-7567-M'NTB -
- APRIL,1987-1 1
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DAY AVERASE DAILY POWER LEVEL-DAY AVERABE DA!LY POWER LEVEL (MWE-Net)
~(MWE. Net) 1 0
17 1140 2
0 18 1139 3
0 19 923 4-0 20 900 5-0 21 899
-6.-
0 22 1040 ss 7
0 23 1138 8
0 24
!!09 9
0 25 1113 10 407 26 1139 1107 27 1107 12
!!42 28
!!23 13 760 29
!!40 14 0
30 1132 I3 00I r
16 1130 ff 4
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UNIT SHUTDOWNS AND PDWER REDUCTIONS DOCKET NO. _QQ:414 Pag 3 1 cf 3 UNI T NAME ;GOTA'eg@_2________
DATE _QQLigt@2_________ -
REPORT. MONTH _______9p_t l_12@2_
COMPLETED BY~_GER@LD_REAVIS____y i
TELEPHONE _12041:323:2062___
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CODE CODE PREVENT RECURRENCE
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l CB l VALVEX REACTOR COOLANT SYSTEM UNIDENTIFIED l
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LEAKAGE OUT OF SPEC (PZR ISOL. VLV.
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38-p 87-4-10 F
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l HEATERS IN SERVICE l
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H HH VALVEX SWAP MAIN STEAM GENERATOR FEED REG l
VALVES 40-p 87-4-10 S
B l --
HB VALVEX CONTROL ^.'ALVE MOVEMENT TEST I
i 41-p 87-4-11 S
B HB l VALVEX CONTROL VALVE MOVEMENT TEST I
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l (1)
(2)
(3)
(4)
F Forced Reason:
Method:
Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram Entry Sheets.For Licensee C-Refueling 3-Automatic Scram Event Report (LER)
D-Regulatory Restriction 4-Other (Explain)
File (NUREG-Ol61)
E-Operator Training & License Examination F-Administrative (S)
G-Operator Error (Explain)
Exhibit I - Same Source H-Other (Explain)
~
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. _59-414___________
ME~_ M 89@8_2________
Pzg3 2 cf 3 DATE _Q5L15282_______.__
REPORT MONTH _______Agr11_19@2_
COMPLETED BY. _ GERALD _REAVIS____
TELEPHONE _12941-323-2562___
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DATE E
HOURS N
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CODE CODE l
PREVENT RECURRENCE 7
87-4-13 F
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1 CB 222222 REACTOR COOLANT SYSTEM UNIDENTIFIED LEAKAGE OUT OF SPEC 42-p 87-4-15 5
B HB VALVEX CONTROL VALVE MOVEMENT TEST I
43-p 87-4-15 F
A HA TURBIN DURING TURBINE TRIP TEST STATOR COOL-l ING WATER DROPPED LOAD 44-p 87-4-18 S
F ZZ L ZZZZZZ POWER DECREASE PER DISPATCHER REQUEST 45-p 87-4-19 S
F ZZ ZZZZZZ POWER DECREASE PER DISPATCHER REQUEST 46-p 87-4-22 F
A RB CONROD OVERPOWER ROD STOP RECEIVED ON "N-44"'
47-p 87-4-24 S
B HA TURBIN TURBINE ACCEPTANCE TESTING (1)
(2)
(3)
(4)
F Forced Reason:
Method:
Exhibit G- ' Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram Entry Sheets For Licensea C-Refueling 3-Automatic Scram Event Report (LER)
D-Regulatory Restriction 4-Other (Explain)
File (NUREG-0161)
E-Operator Training & License Examination F-Administrative (5)
G-Operator Error (Explain)
Exhibit I - Same Source H-Other (Explain)
UNIT SHUTDOWNS'AND POWER. REDUCTIONS DOCKET NO.
50-414" UNIT NAME _GATAWBA_2________
P gs 3 of 3
'DATE~ 05/15/87 REPORT MONTH _______Agt11_1282_
COMPLETED BY _ GERALD _REAL/IS____
TELEPHONE _12041-323-2562___
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HOURS-N R/X NO.
CODE CODE PREVENT RECURRENCE 48:p l 87-4-24 S i B
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1 49-p 87-4-24 5_
B HA TURBIN TURBINE ACCEPTANCE TESTING I
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F ZZ ZZZZZZ POWER ON HOLD PER DISPATCHERS' REQUEST i
I 51-p 87-4-27 S
B HA TURBIN TURBINE ACCEPTANCE TESTING 52-p 87-4-27 S
B HA TURBIN TURBINE ACCEPTANCE TESTING' 53-p 87-4-28 S
A HB 222222 INVALID SECONDARY THERMAL OUTPUT.
DURING TURBINE ACCEPTANCE TEST RECOVERY l
l 1
(1)
(2)
(3)
(4)
F Forced Reason:
Method:
Exhibit G - In=tructions-S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparatico of Data B-Maintenance or test 2-Manual Scram Entry Sheets For Licensee-C-Refueling 3-Automatic Scram Event Report (LER)
D-Regulatory Restriction 4-Other (Explain)
File (NUREG-Ol61)
E-Operator Training & License Examination F-Administrative (5)
G-Operator Error (Explain)
Exhibit I - Same Source H-Other (Explain)
DOCKET NO:
50-414 UNIT:
Catawba 2 DATE:
=5/15/87 NARRATIVE'
SUMMARY
Month: ' April, 1987 Catawba Unit 2 began the month in an outage to repair a Reactor Coolant system leak. On 4/09 at.0100, the unit returned to service, but was forced off line at 0215.when a grease seal between-the exciter and generator failed. The unit was returned to service at 2300 on 4/10 and increased power to 100%. On 4/13 the unit was forced off line due to unidentified leakage. The unit returned to service on 4/15 at 1755,-and increased power to 100%. On 4/19 power was reduced per a request by the Dispatcher and then held power at 80% for testing. The unit increased power to 100% on 4/22 and operated at that level for the remainder of the month.
MONTHLY REFUELING INFORMATION REQUEST 1.
Facility name:-Catawba, Unit 2
- 2. ' Scheduled next refueling shutdown: January, 1988
- 3. - Scheduled restart following refueling: March, 1988 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes
'If yes, what will these be?
Technical Specification Revision
-If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A 5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
N/A
-6.
Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
l -
7.
Number of fuel assemblies (a) in the core:
193 (b) in the spent fuel pool: t-8.
Present licensed fuel pool capacity:
1418 Size of requested or planned increase:
9.
Projected date of last refueling which can be accomsmodated by present licensed capacity:. January, 2013 l
l I
ll i
DUKE POWER COMPANY DATE: May 15, 1987 Name of
Contact:
J. A. Reavis Phone: 704-373-7567 i
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r CATAWBA HUCLEAR STATION MONTHLY OPERATING STATUS REPORT t
1.
' Personnel Exposure For the month of March, no. individual exceeded'10-percent of their allowable annual radiation dose linit.
2.
The total. station, liquid release for March has been compared with'the Technical Specifications maximum ant.ual dose connitment and was less than 10 percent of this limit.
The total station gaseous release fcr March has'been. compared with the Technical'_ Specifications maximum annual dose connitment and was less than 10 percent of this limit.
4
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DUKE POWER GOMPANY P.O. HOX 33180 CHARLOTTE, N.C. 28242 HALB. TUCKER retzenown.
vna reassem=T (704) 373-4531 wimosaa emoovemon
-May 15, 1987
'U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C.
20555 Re: Catawba Nuclear Station Docket No. 50-413 and 50-414
Dear Sir:
Please find attached information concerning the performance and operating status of the Catawba Nuclear Station for the month of April, 1987.
Very t/uly yours, L~-
Hal B. Tucker JAR /20/sbn Attachment' xc:
Dr. J. Nelson Grace, Regional Administrator INPO Records Center U. S. Nuclear Regulatory Commission Suite 1500 Region II 1100 circle 75 Parkway 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Atlanta, Georgia 30323 Mr. Richard G. Oehl, NE-44 Mr. Phil Ross.
U. S. Department of Energy U. S. Nuclear Regulatory Commission 19901 Germantown Road
-MNBB-5715 Germantown, Maryland 20874 Washington, D. C.
20555 American Nuclear Insurers Dr. K. Jabbour, Project Manager c/o Dottie Sherman, ANI Library Office of Nuclear Reactor Regulation The Exchange, Suite 245 U. S. Nuclear Regulatory Commission 270 Farmington Avenue Washington, D. C.
20555 Farmington, CT 06032 Mr. P. K. Van Doorn NRC Resident Inspector Cat.iwba Nuclear Station f/
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