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=Text=
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OPERATING DATA REPORT DOCKET NO.
OPERATING DATA REPORT DOCKET NO.
50-413 DATE      05/15/86 LEPI           04 373-OPERATING STATUS Catawba 1                                              Notes
50-413 05/15/86 DATE LEPI 04 373-OPERATING STATUS Notes
* Nameplate Rating -
* Nameplate Rating -
: 1. Unit Name:
: 1. Unit Name:
: 2. Reporting Period: Aoril 1. 1986-Aoril 30. 1986                                                       per FSAR
Catawba 1
: 3. Licensed Thermal Power (51Wt):                 3411
: 2. Reporting Period: Aoril 1.
: 4. Nameplate Rating (Gross blWe):               1205
1986-Aoril 30. 1986 per FSAR
: 3. Licensed Thermal Power (51Wt):
3411
: 4. Nameplate Rating (Gross blWe):
1205 1145
: 5. Design Electrical Rating (Net SIWE):
: 5. Design Electrical Rating (Net SIWE):
: 6. Staximum Dependable Capacity (Gross blWe):
: 7. Staximum Dependable Capacity (Net SIWE):
1145
1145
!          6. Staximum Dependable Capacity (Gross blWe):
: 7. Staximum Dependable Capacity (Net SIWE):                      1145
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Througli 7) Since Last Report. Give Reasons:
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Througli 7) Since Last Report. Give Reasons:
None
None
: 9. Power Level To Which Restricted,if Any (Net 5tWe):                         None
: 9. Power Level To Which Restricted,if Any (Net 5tWe):
None
: 10. Reasons For Restrictions,if Any:
: 10. Reasons For Restrictions,if Any:
J
J
                                                                            . This alonth         Yr. to Date -           Cumulative
. This alonth Yr. to Date -
,        i1. Ilours in Reporting Period                                         719.0               2 879.0                 7 344.0 l         12. Nur iber Of Hours Reactor Was Critical                             689.3               2 720.2               6 332.5
Cumulative i1. Ilours in Reporting Period 719.0 2 879.0 7 344.0 l
: 13. Reactor Reserve Shutdown llours                                                                                   ---
: 12. Nur iber Of Hours Reactor Was Critical 689.3 2 720.2 6 332.5
: 14. Ilours Generator On Line                                           684.2               7 679_1               6 10 /i . R
: 13. Reactor Reserve Shutdown llours
: 15. Unit Reserve Shutdown Hours                                       ---                    ---                    ---
: 14. Ilours Generator On Line 684.2 7 679_1 6 10 /i. R
: 15. Unit Reserve Shutdown Hours
: 16. Gross Thermal Energy Generated (MWH) 2 286 805 8 613 005 19 30' 185
~
~
: 16. Gross Thermal Energy Generated (MWH)                        2 286 805              8 613 005              19 30' 185
.17. Gross Electrical Energy Generated (MWH) 804 319 3 019 879 6 704 148
      .17. Gross Electrical Energy Generated (MWH)                           804 319           3 019 879               6 704 148
: 18. Net Electrical Energy Generated (MWH) 760 473 2 846 722 6 287 236
: 18. Net Electrical Energy Generated (MWH)                           760 473           2 846 722               6 287 236
: 19. Unit Service Factor 95.2 93.1 84.4
: 19. Unit Service Factor                                                   95.2                     93.1                   84.4
: 20. Unit Availability Factor 95.2 93.1 84.4 j
: 20. Unit Availability Factor                                             95.2                     93.1                   84.4 j       21. Unit Capacity Factor (Using MDC Net) .                               92.4                     86.4                   74.8
: 21. Unit Capacity Factor (Using MDC Net).
: 22. Unit Capacity Factor (Using DER Net)                     .
92.4 86.4 74.8
92.4                   86.4                     74.8
: 22. Unit Capacity Factor (Using DER Net) 92.4 86.4 74.8
: 23. Unit Forced Outage Rate                                                 4.8                     6.9                   15.7
: 23. Unit Forced Outage Rate 4.8 6.9 15.7
,      24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Each):
: 24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Each):
Refueling- August 15, 1986- 10 weeks
Refueling-August 15, 1986-10 weeks
: 25. If Shut Down At End of Report Period. Estimated Date of Startup:
: 25. If Shut Down At End of Report Period. Estimated Date of Startup:
: 26. Units in Test Status (Prior to Commercial Operation):                               Forecast                 Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1
: 26. Units in Test Status (Prior to Commercial Operation):
8605210419 DR              860430                                                                                                       tea 4 ADOCK 0500               3                                                                                     gnj77;         (7
Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1
8605210419 860430 tea 4 DR ADOCK 0500 3
gnj77; (7


AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-413 UNI'T catawba 1
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
                                                                      .DATE 05/15/86 COMPi.ETED'BY   J. A. Reavis TELEPHONE   704/373-7567 MONTH April, 1986 DAY     AVERAGE DAILY POWER LEVEL       DAY     AVERAGE DAILY POWER LEVEL (HWe-Net)                                 (HWe-Ne t)
50-413 UNI'T catawba 1
I           1 142                     17             1 137 2           1 141                     18             1 136 3           1 139                     19               630 4             11.0                     20                 --
.DATE 05/15/86 COMPi.ETED'BY J. A. Reavis TELEPHONE 704/373-7567 MONTH April, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)
5            1 138                     21                 496 6             1 138                     22             1 111 7             1 139                     23             1 140 8             1 136                     24             1 135 9             1 141                     25             1 132 10             1 144                     26~             1 128 11             1 143                     27             1 121 12             1 141                   28               1 128 13 -           1 139                   29               1 129 14             1 136                   30               1 130 15             1 139                   31 16             1 140 INSTRUCTIONS On this format, list the average daily unit power level in HWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(HWe-Ne t)
I 1 142 17 1 137 2
1 141 18 1 136 3
1 139 19 630 4
11.0 20 5
1 138 21 496 6
1 138 22 1 111 7
1 139 23 1 140 8
1 136 24 1 135 9
1 141 25 1 132 10 1 144 26~
1 128 11 1 143 27 1 121 12 1 141 28 1 128 13 -
1 139 29 1 129 14 1 136 30 1 130 15 1 139 31 16 1 140 INSTRUCTIONS On this format, list the average daily unit power level in HWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
I d.
I d.


UNIT SHUTDOWNS AND POWER REDUCTIONS                   DOCKET NO. 50-4J3 UNIT NAME Catawba 1 DATE 5/15/86 REPORT MONTH April, 1986           COMPLETED BY     J. A. Reavis TELEPHONE 704-373-7567 "s_
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-4J3 UNIT NAME Catawba 1 DATE 5/15/86 REPORT MONTH April, 1986 COMPLETED BY J. A. Reavis TELEPHONE 704-373-7567 "s_
O c                o o,$               License               y                       Cause & Corrective 37        "co  v5$                                       af Action to No.                     Date         %  %b               yy                   Event     h"'        gin,   $
O o o,$
                                                $ o-F NE           $
License y
ce
Cause & Corrective c37 "c
                                                                    $5o xmo                Report #  QE mo
v5$
                                                                                                                @E                     Prevent Recurrence av 45-p       86-04-04                   S   --
h"'
B     -
af Action to No.
CC       VALVES     Control Valve Movement Test 5         86-04-19                   F   26.18     A     3                           CB       INSTRU     Reactor Trip Due to Reactor Coolant Loop C Flow Transmitter Replacement 6         86-04-20                   F     8.58     G     3                           IA       ZZZZZZ     Reactor Trip Due to Failure to Block 3                                                                                                                       Source Range Hi Flux Trip Setpoint Euring Startup 46-p       86-04-21                   F   --
Date
B     -
%b yy Event o
CB       ZZZZZZ     Power Increase Delay Due to Reactor Coolant System Leakage Calculations 47-p       86-04-22                   F   --
: gin, NE
A     -
$5o QE
HH       HTEXCH     Power Increase Delay Due to Placing Feedwater Heaters (D1 and EI) into Service 48-p       86-04-26                   F   --
@E Prevent Recurrence F
H     -
o-ce xmo Report #
HC       HTEXCH     Seasonal High Condenser Cooling Water Temperature 49-p       86-04-27                   F   --
mo av 45-p 86-04-04 S
H     -
B CC VALVES Control Valve Movement Test 5
HC       HTEXCH     Seasonal High Condenser Cooling Water Temperature 50-p       86-04-30                   F   --
86-04-19 F
A     -
26.18 A
HH       VALVEX     Feedwater Heater El Shell-Side Drain to Condenser Control Valve Failure 1                                 2                                                       3                         4 Reason:                                                   Method:                   Exhibit G - Instrt.ctions F
3 CB INSTRU Reactor Trip Due to Reactor Coolant Loop C Flow Transmitter Replacement 6
g                       ed         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)
86-04-20 F
D-Regulatory Restriction                                   4-Other (Explain)         File (NUREG-0161)
8.58 G
E-Operator Training 6 License Examination F-Administrative                                                                 5 G-Operational Error (Explain)                                                       Exhibit I - Same Source H-Other (Explain)
3 IA ZZZZZZ Reactor Trip Due to Failure to Block 3
Source Range Hi Flux Trip Setpoint Euring Startup 46-p 86-04-21 F
B CB ZZZZZZ Power Increase Delay Due to Reactor Coolant System Leakage Calculations 47-p 86-04-22 F
A HH HTEXCH Power Increase Delay Due to Placing Feedwater Heaters (D1 and EI) into Service 48-p 86-04-26 F
H HC HTEXCH Seasonal High Condenser Cooling Water Temperature 49-p 86-04-27 F
H HC HTEXCH Seasonal High Condenser Cooling Water Temperature 50-p 86-04-30 F
A HH VALVEX Feedwater Heater El Shell-Side Drain to Condenser Control Valve Failure 1
2 3
4 Reason:
Method:
Exhibit G - Instrt.ctions F
g ed 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-0161)
E-Operator Training 6 License Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit I - Same Source H-Other (Explain)
: (O /77)
: (O /77)


4 DOCKET NO:             50-413 UNIT:               Catawba 1 DATE:               5/15/86 NARRATIVE  
4 DOCKET NO:
50-413 UNIT:
Catawba 1 DATE:
5/15/86 NARRATIVE  


==SUMMARY==
==SUMMARY==
 
Month: April, 1986 Catawba Unit I began April at 100% power but the unit tripped on April 19 during the replacement of a reactor coolanL flow transmitter. The unit returned to service on April 21.
Month: April, 1986 Catawba Unit I began April at 100% power but the unit tripped on April 19 during the replacement of a reactor coolanL flow transmitter. The unit returned to service on April 21.                 Power escalation was delayed to perform Reactor Coolant system leakage calculations, and to place feedwater                                                                     i heaters in service, but the unit reached full power again on April 22.
Power escalation was delayed to perform Reactor Coolant system leakage calculations, and to place feedwater i
heaters in service, but the unit reached full power again on April 22.
t' i
t' i
1 I
1 I
i I
i I
i__. , , . . _.._._..._-._ _.. ___ _ .-. _ _- ,-.-...-._.--_-_.                                              . . . . _ _ . , . _ - - - - _ - . - - - - - _-
i


    . . . .    .    - _..=.   .                  -.                  -- . - . - .          .-            .- - ._    _ .        . _ _
- _..=.
e           i l-   .
e i
,l -
9 I
9 I
MONTHLY REFUELING INFORMATION REQUEST 1
MONTHLY REFUELING INFORMATION REQUEST 1
l
l 1.
!          1. Facility name: Catawba, Unit 1
Facility name: Catawba, Unit 1 2.
: 2. Scheduled next refueling shutdown: August, 1986
Scheduled next refueling shutdown: August, 1986 3.
: 3. Scheduled restart following refueling: October, 1986
Scheduled restart following refueling: October, 1986
[         4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes 4
[
:                If yes, what will these be? Technical Specification Revision I                                                                                                                                         !
4.
If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety j               questions? N/A i
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes 4
: 5. Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 4           6. Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, 4
If yes, what will these be? Technical Specification Revision I
significant changes in design or new operating procedures).                                                             I j           7. Number of fuel assemblies (a) in the core: 193 i                                             (b)   in the spent fuel pool:                                                                                                                                           ,
If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety j
l           8. Present licensed fuel pool capacity: 1418
questions? N/A i
,                Size of requested or planned increase:                   ---
5.
: 9. Projected date of last refueling which can be accommodated by j               present licensed capacity: August, 2008 i                                                                                                                                         '
Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 4
4 2                                                                                                                                         ,
6.
Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
I 4
j 7.
Number of fuel assemblies (a) in the core: 193 i
(b) in the spent fuel pool:,
l 8.
Present licensed fuel pool capacity: 1418 Size of requested or planned increase:
9.
Projected date of last refueling which can be accommodated by j
present licensed capacity: August, 2008 i
4 2
1 1
1 1
i i
i i
j i
j i
1 DUKE POWER COMPANY                                   DATE: May 15, 1986 Name of
1 DUKE POWER COMPANY DATE: May 15, 1986 Name of


==Contact:==
==Contact:==
J. A. Reavis                     Phone:           704-373-7567 I.                                                   - . - - - - . -                          . - . - - -        - . . - .  . . -
J. A. Reavis Phone:
704-373-7567 I.
i
i


CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT
CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT 1.
: 1. Personnel Exposurc
Personnel Exposurc
* v For the month of March, no individual (s) exceeded 10 percent of their allowable annual radiation dose limit.
* v For the month of March, no individual (s) exceeded 10 percent of their allowable annual radiation dose limit.
: 2. The total station liquid release for March has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.
2.
The total station liquid release for March has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.
The total station gaseous release for March has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.
The total station gaseous release for March has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.
i
i


DUKE POWER GOMPANY P.O. box 33189 CHARLOTTE. N.C. 28942 HALH. TUCKER                                                               """
DUKE POWER GOMPANY P.O. box 33189 CHARLOTTE. N.C. 28942 HALH. TUCKER m
m                                                            M""'
M""'
    .m m ., - .
.m m., -.
May 15, 1986 l
May 15, 1986 Director Office of Inspection and Enforcement l
Director Office of Inspection and Enforcement                                           l U. S. Nuclear Regulatory Commission Washington, D. C.       20555                                                   )
U. S. Nuclear Regulatory Commission
1 l
)
Attention: Document Control Desk                                               I Re:     Catawba Nuclear Station Docket No. 50-413
Washington, D. C.
20555 1
l Attention: Document Control Desk I
Re:
Catawba Nuclear Station Docket No. 50-413


==Dear Sir:==
==Dear Sir:==
Please find attached information concerning the performance and operating status of the Catawba Nuclear Station for the month of April, 1986.
Please find attached information concerning the performance and operating status of the Catawba Nuclear Station for the month of April, 1986.
Very truly yours, f.Ad     y Hal B. Tucker JAR: sib I'
Very truly yours, f.Ad y
Attachment xc:     Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900                                     l Atlanta, Georgia 30323 Mr. Phil Ross U. S. Nuclear Regulatory Cosmission MNBB-5715 Washington, D. C. 20555 Dr. K. Jabbour, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Hal B. Tucker JAR: sib Attachment xc:
Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Phil Ross U. S. Nuclear Regulatory Cosmission MNBB-5715 Washington, D. C.
20555 Dr. K. Jabbour, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555


      ._ .. .                                    .  . .          -        -          -          .        = - _ _ _ . -
=
Dir:ctsr
Dir:ctsr May 15, 1986
~;
~;
    .        May 15, 1986
Page Two xc: American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange, Suite 245 270 Farmington Avenue Farmington, CT 06032 INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30323 NRC Resident Inspector Catawba Nuclear Station Mr. Richard G. Oehl, NE-44 U. S. Department of Energy 19901 Germantown Road Germantown, Maryland 20874 r
  .          Page Two xc: American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange, Suite 245 270 Farmington Avenue Farmington, CT 06032 INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30323 NRC Resident Inspector Catawba Nuclear Station
;                        Mr. Richard G. Oehl, NE-44 U. S. Department of Energy 19901 Germantown Road Germantown, Maryland 20874 r
I i
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-.. ~..
_ - _. _ - _ . _ . . - - . - . - _ . ~ . _ - _ _ . _
_. _ - _. _.. - -. -. - _. ~. _ - _ _. _
                                                                                                                                    - __ . .__!._._--_._-}}
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Latest revision as of 15:03, 7 December 2024

Monthly Operating Rept for Apr 1986
ML20205P462
Person / Time
Site: Catawba 
Issue date: 04/30/1986
From: Reavis J, Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8605210419
Download: ML20205P462 (8)


Text

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OPERATING DATA REPORT DOCKET NO.

50-413 05/15/86 DATE LEPI 04 373-OPERATING STATUS Notes

  • Nameplate Rating -
1. Unit Name:

Catawba 1

2. Reporting Period: Aoril 1.

1986-Aoril 30. 1986 per FSAR

3. Licensed Thermal Power (51Wt):

3411

4. Nameplate Rating (Gross blWe):

1205 1145

5. Design Electrical Rating (Net SIWE):
6. Staximum Dependable Capacity (Gross blWe):
7. Staximum Dependable Capacity (Net SIWE):

1145

8. If Changes Occur in Capacity Ratings (Items Number 3 Througli 7) Since Last Report. Give Reasons:

None

9. Power Level To Which Restricted,if Any (Net 5tWe):

None

10. Reasons For Restrictions,if Any:

J

. This alonth Yr. to Date -

Cumulative i1. Ilours in Reporting Period 719.0 2 879.0 7 344.0 l

12. Nur iber Of Hours Reactor Was Critical 689.3 2 720.2 6 332.5
13. Reactor Reserve Shutdown llours
14. Ilours Generator On Line 684.2 7 679_1 6 10 /i. R
15. Unit Reserve Shutdown Hours
16. Gross Thermal Energy Generated (MWH) 2 286 805 8 613 005 19 30' 185

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.17. Gross Electrical Energy Generated (MWH) 804 319 3 019 879 6 704 148

18. Net Electrical Energy Generated (MWH) 760 473 2 846 722 6 287 236
19. Unit Service Factor 95.2 93.1 84.4
20. Unit Availability Factor 95.2 93.1 84.4 j
21. Unit Capacity Factor (Using MDC Net).

92.4 86.4 74.8

22. Unit Capacity Factor (Using DER Net) 92.4 86.4 74.8
23. Unit Forced Outage Rate 4.8 6.9 15.7
24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Each):

Refueling-August 15, 1986-10 weeks

25. If Shut Down At End of Report Period. Estimated Date of Startup:
26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1

8605210419 860430 tea 4 DR ADOCK 0500 3

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-413 UNI'T catawba 1

.DATE 05/15/86 COMPi.ETED'BY J. A. Reavis TELEPHONE 704/373-7567 MONTH April, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)

(HWe-Ne t)

I 1 142 17 1 137 2

1 141 18 1 136 3

1 139 19 630 4

11.0 20 5

1 138 21 496 6

1 138 22 1 111 7

1 139 23 1 140 8

1 136 24 1 135 9

1 141 25 1 132 10 1 144 26~

1 128 11 1 143 27 1 121 12 1 141 28 1 128 13 -

1 139 29 1 129 14 1 136 30 1 130 15 1 139 31 16 1 140 INSTRUCTIONS On this format, list the average daily unit power level in HWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

I d.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-4J3 UNIT NAME Catawba 1 DATE 5/15/86 REPORT MONTH April, 1986 COMPLETED BY J. A. Reavis TELEPHONE 704-373-7567 "s_

O o o,$

License y

Cause & Corrective c37 "c

v5$

h"'

af Action to No.

Date

%b yy Event o

gin, NE

$5o QE

@E Prevent Recurrence F

o-ce xmo Report #

mo av 45-p 86-04-04 S

B CC VALVES Control Valve Movement Test 5

86-04-19 F

26.18 A

3 CB INSTRU Reactor Trip Due to Reactor Coolant Loop C Flow Transmitter Replacement 6

86-04-20 F

8.58 G

3 IA ZZZZZZ Reactor Trip Due to Failure to Block 3

Source Range Hi Flux Trip Setpoint Euring Startup 46-p 86-04-21 F

B CB ZZZZZZ Power Increase Delay Due to Reactor Coolant System Leakage Calculations 47-p 86-04-22 F

A HH HTEXCH Power Increase Delay Due to Placing Feedwater Heaters (D1 and EI) into Service 48-p 86-04-26 F

H HC HTEXCH Seasonal High Condenser Cooling Water Temperature 49-p 86-04-27 F

H HC HTEXCH Seasonal High Condenser Cooling Water Temperature 50-p 86-04-30 F

A HH VALVEX Feedwater Heater El Shell-Side Drain to Condenser Control Valve Failure 1

2 3

4 Reason:

Method:

Exhibit G - Instrt.ctions F

g ed 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-0161)

E-Operator Training 6 License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit I - Same Source H-Other (Explain)

(O /77)

4 DOCKET NO:

50-413 UNIT:

Catawba 1 DATE:

5/15/86 NARRATIVE

SUMMARY

Month: April, 1986 Catawba Unit I began April at 100% power but the unit tripped on April 19 during the replacement of a reactor coolanL flow transmitter. The unit returned to service on April 21.

Power escalation was delayed to perform Reactor Coolant system leakage calculations, and to place feedwater i

heaters in service, but the unit reached full power again on April 22.

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MONTHLY REFUELING INFORMATION REQUEST 1

l 1.

Facility name: Catawba, Unit 1 2.

Scheduled next refueling shutdown: August, 1986 3.

Scheduled restart following refueling: October, 1986

[

4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes 4

If yes, what will these be? Technical Specification Revision I

If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety j

questions? N/A i

5.

Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 4

6.

Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).

I 4

j 7.

Number of fuel assemblies (a) in the core: 193 i

(b) in the spent fuel pool:,

l 8.

Present licensed fuel pool capacity: 1418 Size of requested or planned increase:

9.

Projected date of last refueling which can be accommodated by j

present licensed capacity: August, 2008 i

4 2

1 1

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1 DUKE POWER COMPANY DATE: May 15, 1986 Name of

Contact:

J. A. Reavis Phone:

704-373-7567 I.

i

CATAWBA NUCLEAR STATION MONTHLY OPERATING STATUS REPORT 1.

Personnel Exposurc

  • v For the month of March, no individual (s) exceeded 10 percent of their allowable annual radiation dose limit.

2.

The total station liquid release for March has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

The total station gaseous release for March has been compared with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

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DUKE POWER GOMPANY P.O. box 33189 CHARLOTTE. N.C. 28942 HALH. TUCKER m

M""'

.m m., -.

May 15, 1986 Director Office of Inspection and Enforcement l

U. S. Nuclear Regulatory Commission

)

Washington, D. C.

20555 1

l Attention: Document Control Desk I

Re:

Catawba Nuclear Station Docket No. 50-413

Dear Sir:

Please find attached information concerning the performance and operating status of the Catawba Nuclear Station for the month of April, 1986.

Very truly yours, f.Ad y

Hal B. Tucker JAR: sib Attachment xc:

Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Phil Ross U. S. Nuclear Regulatory Cosmission MNBB-5715 Washington, D. C.

20555 Dr. K. Jabbour, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555

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Dir:ctsr May 15, 1986

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Page Two xc: American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange, Suite 245 270 Farmington Avenue Farmington, CT 06032 INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30323 NRC Resident Inspector Catawba Nuclear Station Mr. Richard G. Oehl, NE-44 U. S. Department of Energy 19901 Germantown Road Germantown, Maryland 20874 r

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