ML20003F749: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(StriderTol Bot change)
 
Line 20: Line 20:
i j                          TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR P0kIR    ,
i j                          TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR P0kIR    ,
SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT MARCH 1, 1981 - MARCH 31, 1981 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 1
SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT MARCH 1, 1981 - MARCH 31, 1981 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 1
;
Submitted By: -        se        o_is su Plant superintendent l
Submitted By: -        se        o_is su Plant superintendent l
810_4gggg2q                          .
810_4gggg2q                          .
Line 172: Line 171:


UNIT SilUTDOWNS AND POWER REDUCTIONS              DOCKET No.            50-327 UNIT NAtlE          Sc.quoyah_1 DATE        April 1, 1981 C0t1PLETED BY          Mike Eddings REPORT t10NTil    March                    TELEPIIONE        (615) 842-0215 s
UNIT SilUTDOWNS AND POWER REDUCTIONS              DOCKET No.            50-327 UNIT NAtlE          Sc.quoyah_1 DATE        April 1, 1981 C0t1PLETED BY          Mike Eddings REPORT t10NTil    March                    TELEPIIONE        (615) 842-0215 s
S cm  n    % ee 8        Licensee                  U                  Cause & Corrective No.                                                        Date  %      .S C  E  .o S E          Event        E%        E*e                      Action to p      $$    $  S      E. Report #      $$          $                Prevent Recurrence
S cm  n    % ee 8        Licensee                  U                  Cause & Corrective No.                                                        Date  %      .S C  E  .o S E          Event        E%        E*e                      Action to p      $$    $  S      E. Report #      $$          $                Prevent Recurrence e5    a                                &          o" o
;
e5    a                                &          o" o
                                                                                                                                                 "."S{
                                                                                                                                                 "."S{
2: en o
2: en o

Latest revision as of 21:55, 17 February 2020

Monthly Operating Rept for Mar 1981
ML20003F749
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 04/01/1981
From: Eddings M
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20003F746 List:
References
NUDOCS 8104230520
Download: ML20003F749 (12)


Text

. _. . _ - _ _

i j TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR P0kIR ,

SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT MARCH 1, 1981 - MARCH 31, 1981 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 1

Submitted By: - se o_is su Plant superintendent l

810_4gggg2q .

TABLE OF CONTENTS.

Op e ra tions S umma ry . . . . . . . . . . . . . . . . . . . ,. . . . . . . . 1-2 PORV's and Safety Valves Summary . . . . . . . . . . . . . . . . . . . . 2 Significant Operational Events . . . . . . . . . . . . . . . . . . . . . 3-4 Average Daily Unit Power Level . . . . . . . . . . . . . . . . . . . . . 5 Operating Data Report ......................... 6 Unit Shutdown and Power Reduction ................... 7 Plant Maintenance Summarry ....................... 8 Outage Maintenance Summa ry . . . . . . . . . . . . . . . . . . . . . . . 9-10

/

Operations Summary March, 1981 The following summary describes the significant operational activities for the month of March. In support of this summary, a chronological log of significant events is included in this report. ,

There were eleven Licensee Event Reports and one Special Report during March.

There were two scrams during March.

Unit I was critical for 336.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, produced 305,250 MWH(gross)with 5.72 percene station use, resulting in an average hourly gross load of 987,129 KV during the month. The net heat rate for the month was 10,670 BTU /KWH.

There are 331.95 full power days estimated remaining until the end of cycle 1 fuel. With a capacity factor of 85 percent the target EOC exposure would be reached April 25, 1982. The capacity factor for the month was 33.7 percent.

Unit I remained in mode 5 for repairs on the generator exciter and de-contamination due to containment spray down on February 11, 1981, until March 7, 1981. The unit was brought critical and tied on line at 0940 on March 12.

At 1725 on March 12, the unit was taken off line for a turbine balance shot.

On March 13, the unit was again tied on line at 0349 but had to be removed from i

service at 1118 for another balance shot. At 1819, March 13, the unit was agaa tied on line but sustained a reactor trip (reactor trip 9) at 1159 on March 14.

The trip occurred when the air line to number 3 steam generator regulating valve blew off, failing the valve close, and causing a low level in the steam generator.

The unit was returned to service on March 17, at 0233 and again tripped (reactor trip #10) at 1804 on March 17 when control rod N5 dropped into the core. A bad 1- ,

\

m _ _ _ --

~ _ _ _ . . _ . _ . . . , _ , . - _ _ . . - _ _

Operations Summary (Continued) connection on the electromagnets was discovered to be th<: cause of the rod drop.

The unit returned to service at 0311 on March 21 and taken up to 98% reactor power,1100MW(e). At 1118 on March 22, the unit experienced a turbine run-back to a reactor power level of 65%, 720 MW(e). The run-back was caused by exceeding a RCS loop over-temperature AT limit. The limit has subsequently been re-adjusted after better data was available.

At 2400 March 31, 1981, the unit was in mode 1 at 96% reactor power, generating 1086 MW(e).

PORV's and Safety Valves Summary No pressure operated relief safety valves were challenged during the month.

I 1

e 1

2- ,

, ~ - - . , . . . - - ,

.-r- --. ,-- , - - - - - - , - - - . - - - - , - ,e ,-,

~

Significant Operational Events Date Time - Event 03/01/81 0001 Unit I fa mode 5 - Outage continued for repairs on the generator exciter and de-contamination due to congainment spray down on February 11, 1981.

03/02/81 2138 Began heatup.

03/07/81 2219 Entered mode 4.

03/12/81 0545 Rx critical.

0810 Entered mode 1.

0843 Rolled turbine.

0940 Unit 1 tied on line, increasing power to 20%.

1120 Increasin 1250 Rx Pwr 30%g power

- Holding from 345 20%

MW(e) to 30%.

- RCS dilution.

1600 Began shutdown for balance shot.

1725 Generator off line - mode 2.

1825 Turbine tripped.

2005 Broke vacuum on main condenser.

03/13/81 2338 Re-established vacuum on main condenser.

0240 Entered mode 1.

0349 Unit 1 tied on line.

1017 Rx Pwr 25% - Began decreasing load -

Balance shot.

1118 Generator off line.

1310 Broke vacuum on main condenser.

1448 Re-established vacuum on main condenser.

1749 Rolled turbine.

1752 Entered mode 1.

1819 Unit I tied on line at 8%.

2005 Began increasing load to 30%.

2039 Rx Pwr 34% - Holding.

2330 Began increasing pwr.

03/14/81 0047 Rx Pwr G %.

0855 Began increase to 60% Rx pwr.

1100 Load at 60% holding.

1159 Reactor Trip #3 S/G reg. viv. air line blew off (1-FCV-3-90 .

03/17/81 0017 Rx crit.ical.

0145 Entered mode 1.

0233 Generator tied on line.

0310 Increased Rx pwr to 30%.

Significant Operational Events (Continued)

Date Time Event

~

03/17/81 0530 Rx Pwr 50% @ 40% load.

1102 Began increase to 60% load.

1247 Holding load at 60%.

1315 Began load increase to 75,%.

1615 Load at 75% - Holding.

1745 Began load increase to 90%.

1804 Reactor Trip #10, control rod N5 dropped due to bad connector to the electromagnets.

03/18/81 0058 Began cooldown to mode 5 to investigate and repair control rod problem.

1609 Unit 1 entered mode 5.

03/19/81 1601 Entered mode 4.

03/21/81 0018 Reactor critical.

0132 Entered mode 1.

0235 Rolled turbine.

0311 Generator tied on line 0600 Rx Pwr 30% - 290 W(e), Rx Pwr at 8%.

0655 Began load increase.

1000 Holding load at 50%.

1110 Increasing load to 90%.

1350 Holding load at 85%.

1420 Increasing load to 90%.

2200 Increase to 98%.

03/22/81 0600 Rx Pwr 98% - 1100 W(e).

03/22/81 1105 Began increasing power to 100%.

1118 Turbine run-back - Rx Pwr 65%, 720 W(e).

1159 Increased power to 98%.

1400 96.7% power.

03/31/81 2400 Unit in mode 1, Rx Pwr 96%, 1086 W (e).

i 4- ,

n-- - -

e AVERAGE DAILY UNIT POWER LEVEL.

d

DOCKET NO. 50-327

, UNIT Sequoyah 1

~

DATE' 4-1-81 COMPLETED BY Mike Eddings TELEPHONE (615) 842-0295' MONTH March DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P0hTR LEVEL (MWe-Net) (MWe-Net) 1 0 17 381 2 0 18 0 3 0 . 19 0 4 0 20 0 -

5 0 21 634 6 0 22 1082 7 0 23 1088 8 0 24 1083

.9 0 25 1070 10 0 26 1081' 11 0 27 1073 12 64 28 1067 13 142 29 1058 14 258 30 1064 15 0 31 1041 16 0 i

l INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

/

-5 ,

. .- _ _ , - _ - _ ~ _ _ _ _ . - - _ . _ _ - , _ _ . - . - _ . . - - _ , _ . - . . . _ - ., . - _

OPERATING DATA REPORT DOCKET NO. 50-327

~ DATE April 1, 1981 COMPLETED BY Mike Eddings TELEPHONE (615) 842-0295 OPERATING STATUS

1. Unit Name: Sequovah 1 Notes
2. Reporting Period: March 1981
3. Licensed Thermal Power (MWt): 3411
4. Nameplate Rating (Sross MWe): 1220.53
5. Design Electrical dating (Net MWe): 1148
6. Maximum Dependable Capacity (Gross MWe): 1183__
7. Maximum Dependable Capacity (Net MWe): 1148
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Pericd 744 2160 9505
12. Number of Hours Reactor Was Critical 336.0 1027.9 2566.5
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 309.2 871.7 1709.39
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 899,560 2,512,327 4,184,357-
17. Gross Electrical Energy Generated (MWH) 305,250 873.800 1,431,121
18. Net Electrical Energy Generated (MWH) 237,784 829.494 1,348.334
19. Unit Service Factor 41.6 40.4 18.0
20. Unit Availability Factor 41.6 40.4 18.0
21. Unit Capacity Factor (Using hDC Net) 33.) 33.4 12.4
22. Unit Capacity Factor (Using DER Net) 33.7 33.4 12.4
23. Uni Forced Outage Rate 58.4 59.6 82.0
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25. If Shut Down At End Of Report Period, Estinated Date of Startup:
26. Units In Test Status (Prior to Ccomercial Operation):

Forecast Achieved INITIAL CRITICALITY 7-4-30 7-5-30 INITIAL ELECTRICITY 8-21-50 7-22-80 COMP.:.RCIAL OPERATION 5-1-31

,(9/77)

_g.

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-327 UNIT NAtlE Sc.quoyah_1 DATE April 1, 1981 C0t1PLETED BY Mike Eddings REPORT t10NTil March TELEPIIONE (615) 842-0215 s

S cm n  % ee 8 Licensee U Cause & Corrective No. Date  % .S C E .o S E Event E% E*e Action to p $$ $ S E. Report # $$ $ Prevent Recurrence e5 a & o" o

"."S{

2: en o

u 8 81 03 01 F 273.7 A 4 Steam dump FCV-1-111 failed open causing #2

, S/G to get hi-high S/G 1evel.

27 81 03 12 F 10.4 B 5 Generator balance shot.

28 81 03 13 F 7.0 B 5 Generator balance shot.

I 9 81 03 14 F 62.6 A 3

~

Air line to #3 S/G F.W. reg. valve blew off at 7 soldered joint (1-FCV-3-90). Soldered joint repaired.

10 81 03 17 F 81.1 A 3 Control rod NS dropped into core. connections to electromagnets bad. Connections repaired and cleaned.

I 2 3 4 F: Forced Reason: Hethod: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-fla nua l for Preparation of Data-B-tfaintenance or Test 2-tfanual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-

, D-Regulatory Restriction 4-Cont of Existing 0161)

E-Operator Training & License Examination Outage F-AIministrative 5-Reduction G-Operational Error (Explain) 9-Other 5 (9/77) II-Other (Explain) Exhibit I-Same Source

Plant Maintenance Summary The following significant maintenance items were completed during the month of March,1981:

Mechanical Maintenance

1. Rebuilt auxiliary control air compressor B-B du'e to broke crank shaft.
2. Machined the seat and plug and rebuilt the steam generator level control valve 1-LCV-3-171.
3. Rebuilt the compressor on glycol chiller package B.

Electrical Maintenance

1. Replaced the switch compartment heaters in 97 valves and realaced the geared limit switches in 19 valves associated with the IRCW and CCS systems.
2. Replaced the bearings in the 1A motor driven auxiliary feedwater Pump.
3. Replaced defective components in the control circuit for the pressurizer heater ID.
4. Removed the fuse failure alarm relay from service per CAR #21-81-22.
5. Replaced coils in the D/G LRX relays.
6. Investigated problems with the incore instrumentation 10-path transfer device.
7. Investigated problems with the generator core monitor system.
8. Unit 1 ice basket weighing and adding ice was completed as per tech specs.
9. Investigated and repaired connector associated with N-5 control rod lift coils.

Instrument Maintenance

1. Replaced 15V and 48V power supplies in Unit 1 SSPS with newer models to resolve design problems.
2. Replaced Unit I steam flow transmitters to resolve AP discrepancies with actual flow.
3. Replaced Unit 1 pressurizer variable heater controls which had caused breaker failure by excessive actuations.

i

Outage Maintenance Summary March, 1981 The following significant maintenance items were completed during the month of March, 1981.

Unit 1 ,

1. Repairs were completed on the main generator and exciter and they were reassembled to be returned to service.
2. The main generator was leak tested.
3. Completed the addition of a vent line between the condensate pot vent and the pressurizer vapor space sample line. This work was done per ECN 5392 to improve the pressurizer level indications.
4. Post-modification testing was conducted on all 32 hydrogen igniters.

The inspections and tests satisfies the new tech spec requirements.

5. Work continues on the hanger problem as per IE Bulletin 79-14.

All work affecting Unit I startup and operation has been completed.

6. As per ECN 5404, all electrical penetrations of the Unit 1 airlocks were resealed in order to avoid a possible break of containment isolation.
7. Work continues in the re-routing of conduit and cable serving train B of the ERCW and fire pumps. This work to satisfy NRC commitments.
8. Completed the addition of structural reinforcement to masonry block walls in the auxiliary building as per NRC SQN CEB 8030.
9. To satisfy NRC commitments work continued on coating cables outside of primary containment with flamatic.

Unit 2

1. Work continues to provide craft and engineering support for pre-operational hot functional testing of Unit 2.
2. Work was completed on re-routing the feedwater pump oil tank
piping. .

Unit 0 Or Items Affecting Unit 1 and 2

1. Began work to add permanent yard security lighting to satisfy footcandle requirements.

Outage Maintenance Summary -(Continued)

March, 1981 Unit 0 Or Items Affecting Unit 1 and 2

2. Work progressed to revise piping to the HVAC equipment serving the electrical board rooms and the main control room. This re-vision will increase ERCW flow and avoid corros, ion problems.
3. Installation of the perimeter alert II detection system in the security alarm station is 80 percent complete. Testing is still in progress.

e

~ - - ~ ~ - + + - . ,-m + - - ,