ML20050C761

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Monthly Operating Repts for Oct 1981
ML20050C761
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/05/1981
From: Eddings M
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20050C760 List:
References
NUDOCS 8204090335
Download: ML20050C761 (13)
v • d • e


Text

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j DIVISION OF NUCLEAR POWER l

! SEQUOYAH NUCLEAR PLANT I

MONTHLY OPERATING REPORT 4

OCTOBER 1, 1981 - OCTOBER 31, 1981 1

4 l

UNIT 1 1

DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77

'l 1

l j UNIT 2 i ,

[ DOCKET NUMBER 50-328

!. LICENSE NUMBER DPR-79 i

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i Submitted By: [bb Power Plant Superintendent I

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8204090335 811116 PDR ADOCK 05000327 N

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TABLE OF CONTENTS Operations Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . . . . . . . 1-2 PORV's and Safety Valves Summary . . . . . . . . . . . . . . . . . . . . . 2 Licensee Events and Special Reports . . . . . . . . . . . . . . . . . . . 2 Offsite Dose Calculation Manual Changes . . . . . . . . . . . . . .. . . 2 Operating Data ,

4 Unit 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-5 Unit 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-8 /

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Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . . 9 q (I outage Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . . 9-11 s

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1 Operations Summary q i s, ,

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The'follotingsummarydescribesthesijnif'icantoperationalactivities for the month)cf Oct ober. In support of this summ'ary, a chronological log

,of significant events is included in this report.

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"\ -3 Unat 1 ,

Unit I was cr \tical for 86.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, iproduced 22,230 MWH (gross) with 47.16 percent stafion use, resulting in af average hourly gross load of

, , ,* 316,441 KW during the.;mhnth.. The net heat rate for the month was 24,976

. ,. BTU /KWH. Therp are 225.4 full power days estimated remaining until the end

' " of cycle I fuel! With a capacity factor of 85 percent' the target EOC ex-

.posure would be reached July 23, 1982. The capacity factor for the month

  • - Wys 2.6 percent.,3 - .

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There Nere no reactor scrams, nenual shutdowns, or power reductions u . .

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- A Preoperational and pr ..[aJity testing continued during the month.

4 x Significant Operational _.tvents

, e Unit 1 ,'

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Date ,i Time ~ { Event 10/01/81 0001- S Reactor in mode 5 - Outage continues.

4 i

. 10/22/81 '

)' ,0953 ~I The' rea;' tor.:entared mode 4.

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0 10/24/81 2140 The reactor entered mode 3.

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10/28/~81 . . :~ +

0917 Thi [eactor 'taken critical.

2054 .The reactor -

  • entered mode 1.

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1 10/29/81 0121 G$nerator tied on line.

x 1107 Reactor at 28% power, producing 250 MWe.

10/31/81 2359 Holding reactor power at 80%, pro-ducing 828J W .

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Significant Operational Events (Continued)

. Unit 2

.Date Time Event

10/01/81 0001 Reactor in mode 5 - Outage continues.

l 10/28/81 2210 Reactor entered mode 4.

10/31/81 2359 Reactor in mode 4 at 340*F, 800 psi.

PORV's and Safety Valves Summary r

No PORV's or safety valves were challenged during the month. l 4

l Licensee Events and Special Reports  !

i The following Licensee Event Reports (LER's) were sent during October 1981, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.

l SQRO-50-327/117 Waste gas disposal system oxygen analyzer 2

inoperable due to out of calibration caused

by inadvertent movement of zero adjustment control. ,

i l SQR0-50-327/118 Radiation monitors 1-RE-90-106 and -112 out j of service simultaneously during leak testing of containment isolation valves.

l SQRO-50-327/119 Pipe plugs missing from penetrations X-1, f

! X-108, and X-109 due to personnel error.

SQRO-50-327/120 Re-calculation of post accident water level ,

in contaitment revealed some class IE components would fail.

SQRO-50-327/121 Flux imbalance penalty function generator, XM-92-5005K, inoperable due to out of calibra-tion.

i Special Reports

)

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No special reports were sent during the month of October.

Offsite Dose Calculation Manual Changes There were no changes to the Offsite Dose Calculation Manual during the month of October 1981.

OPERATING DATA REPORT DOCKET NO. 50-327 DATE 11/0s/81 COMPLETED BY M. Eddings TELEPil0NE (613) 842-0295 OPERATING STATUS

1. Unit Name: Sequoyah One Notes
2. Reporting Period: nernher 1981

, 3. Licensed Thermal Power (flWL): 3411

4. Nameplate Rating (Gross t!We): 1220J8
5. Design Electrical Rating (Net MWe): 1128
6. Maximum Dependable Capacity (Gross !!We): 1161
7. Maximum Dependable Capacity (Net MWe): 1128 _
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

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9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restriqtions, If Any:

This Month Yr-to-Date Cumulative

11. Ilours in Reporting Period 745 __ 2977 2977
12. Number cf Ilours Reactor Was Critical gg3 its4_n 14s4_8 13 Reactor Reserve Shutdown liours n n 0
14. Hours Generator On-Line 76 7 19g7.1 1387_,3
15. Unit Reserve Shutdown flours n 0 0
16. Gross Thermal Energy Generated (MWil) n;#8_. -_1,ngs;n12 __1,n85,032 .
17. Gross Electrical Energy Generated (MWil) --_22,230 1.qnn_Asn 1,1aQ,_4 5 0 . .
18. Net Electrical Energy Generated (tM ) 11;2/.6 1.307.777- 1.307.770
19. Unit Service Factor 9.5 ~ 46.9 46.9 -
20. Unit Availability Factor os 46.9 46.9
21. Unit Capacity Factor (Using MDC Net) 1.4 39J 39.3
22. Unit Capacity Factor (Using DER Net) I m4 39.3 39.3 i 23. Unit Forced Outage Rate yp __ g n . s _ 51 1 53.1
24. Shutdowns Scheduled Over Next 6 tionths (Td), and Duration of Each): ,

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

Forecast Achieved INITIAL CRITICALITY 7-4-80 7-5-80 INITIAL ELECTRICITY R-71-Rn 7-22-80 COMMERCIAL OPERATION h al_. 7-1-R1 (9/77)

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. s0-327 UNIT. Senuoyah_Dat DATE 11/05/81 COMPLETED IlY li.._Eddings TELEP110NE (615) 842-0225 MONTil October DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (!!We-Ne t )

  • 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 3 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 143 14 0 30 205 15 0 31 440 16 o 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)

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OPERATING DATA REPORT

, DOCKET NO. 50-328 DATE 11/05/81 COMPLETED BY David Dupree TELEPIIONE (615) 842-0295 OPERATING STATUS

1. Unit Name: Sequoyah Two Notes
2. Reporting Period: octnber 19g1
3. Licensed Thermal Power (MWL): 3411
4. Nameplate Rating (Gross MWe): 19?n_s
5. Design Electrical Rating (Net NWe): _ytta
6. Maximum Dependable Capacity (Gross MWe): 1185
7. Maximum Dependable Capacity (Net MWe): 1143__
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

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9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month Yr-to-Date Cumulative

11. Ilours in Reporting Period NA NA NA
12. Number of Ilours Reactor Was Critical NA NA NA
13. Reactor Reserve Shutdown llours NA NA NA
14. Ilours Generator On-Line NA NA NA
15. Unit Reserve Shutdown llours NA NA NA
16. Gross Thermal Energy Generated (MWH) NA NA NA
17. Gross Electrical Energy Generated (MWil) NA NA NA
18. Net Electrical Energy Generated (MWil) NA NA NA
19. Unit Service Factor NA NA NA
20. Unit Availability Factor NA _

NA NA

21. Unit Capacity Factor (Using MDC Net) NA NA __

NA

22. Unit Capacity Factor (Using DER Net) NA NA NA
23. Unit Forced Outage Rate NA NA NA
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Six months after initial criticality technical specification ice reichine_

rc. quired maintenanceapprovir nrelv 2g dnvn.

25. If Shut Down At End Of Report Period, Esiimated Date of Startup: 11-s_st
26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 11-5-81 NA INITIAL ELECTRICITY 11-25-81 NA COMMERCIAL OPERATION 1-1-83 NA (9/77)

AVERAGE DAILY UNIT POWER LEVEL j

DOCKET NO.10-328 UNIT Requoy.ah_Tm  !

DATE 11/_05181

COMPLETED BY David 3)upne TELEPil0NE (fil51_fL42-0295 MONTli October i

l DAY AVLRAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL  ;

(MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 I l 5 0 21 0 6 0 22 0 7 _ 0 23 0 8 0 24 0 1 9 0 25 0

10 0 26 0 a

11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 f 15 0 31 0 16 0 1

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.

i (9/77)

____m_..._ . _ _ _ _ . . _ _ _ _ _ _ _ _ . . . _ . _ _

UNIT SHUTDOk'NS AND P0k'ER REDUCTIONS DOCKET NO. 50-328 UNIT NAME St.quoyah Two  !

DATE 11/05/81 . ;

COMPLETED BY navia nispree REPORT MONTil October TELEPHONE (615) 842-0295 W

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Licensee u c^ ca o ec u c Cause & Corrective No. Date ".c. .S $

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.e j y ouo Event $$ g*o O *U Action to '

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R 2e 2 $"* "g 'g g.g Prevent Recurrence l

$~ $N5 O 81/10/01 S 745 B 4 Pre-criticalfty Testing and Maintenance i

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e 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) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)

E-Operator Training & License Examination Outage F-Administrative 5-Reduction i G-Operational Error (Explain) 9-Other 5

! (9/77) H-Other (Explain) Exhibit I-Same Source i

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Plant Maintenance Summary i

I The following significant maintenance items were completed during the 4

month of October 1981: .

i Mechanical Maintenance

, 1. Replaced the inboard seals and rebuilt outboard seal due to leakage on I

centrifugal charging pump 2B-B.

l 2. Inspected and rebuilt all four service air compressors.

i j 3. Replaced the shaft and impeller on #3 heater drain tank pump IC. I

} 4. Repaired the motor driven auxiliary feedwater pump pressure control i valves 2-PCV-3-122 and 2-PCV-3-132. 1 l

S. Replaced the main flange gasket on Unit 2 reactor coolant pump #2.

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6. Replaced the mechanical seal on hotwell pump 1A.

i l

j Electrical Maintenance

1. Investigated the Unit 2 balance of plant instrumentation functuations.

l l 2. Repaired the oil lift systems on Unit I reactor coolant pumps 1, 2 and 3.

3. Replaced the immersion heater on IB-B diesel generater.
4. Repaired the motors on auxiliary feedwater pumps IA-A, 2A-A, and 2B-B.

j 5. Replaced a 3-cell unit on diesel generator battery 1A-A.

6. Repaired the 2B hotwell pump motor s

7 Replaced the 1B condenser vacuum pump motor.

l Instrument Maintenance i None reportable.

i Field Services Maintenance

! Unit I

1. To satisfy the technical specifications, 527 inaccessible snubbers on Unit I was inspected.
2. Work continues on the installation of a post accident sampling system which will add the capability of obtaining designated liquid and gas _

! samples during and after a postulated event.

I I

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Field Services Maintenance (Continued)

Unit 1

3. Two pinholes in the outer c'asing at the center line of the Unit 1 generator have been seal welded.
4. A reactor vessel head venting is being installed as required per TMI Lessons Learned LL-2.1.13.
5. Machining of the reactor cavity is complete. This allows an inflatible cavity seal ring to be installed during refueling outages to prevent refueling water from entering the annulus.
6. The electrical penetration cap has been replaced with a QA qualified cap on the 734' personnel airlock.
7. The relocation of various main control board instruments to enhance functional layout and grouping is complete.
8. Thermocouple cables have been installed between upper and lower contain-ment to monitor supports and equipment while they are returning to service.
9. 1-PT-68-68 and its associated panel have been relocated from the raceway to an accumulator room.
10. The RCS hot leg RTD cables terminated in junction boxes below the pro-jected flood level of Unit I and 2 have been replaced with class IE in line Raychem splices.
11. Because of the re-evaluation of the flood Icvel inside containment, hydrogen igniters on circuits 10 and 11 have been re-wired.
12. Reactor coolant pump #1 motor was replaced during the outage.

Unit 2

1. A reactor coolant sampling system is being installed.
2. PS-81-5A, -5B, -9A, and -9B have been replaced with pressure differential indicating switches. They have been calibrated and functionally tested.
3. Because of the re-evaluation of the flood level inside containment, the hydrogen igniters have been re-wired.

Unit 0 or Items Affecting Both Units

1. Work continued on a temperature monitoring system being installed on various class IE electrical equipment.
2. To prevent a reactor trip due to a turbine trip when the reactor power is below 50%, the SSPS and NIS power range drawers N41, N42, N43 and N44 have been modified to incorporate P-9 permissive for turbine / reactor trip logic.

Unit 0 or Items Affecting Both Units (Continued)

3. All twenty-nine fire deluge valves have had the 3-way alarm test valves replaced with two ball valves and one swing check valve.
4. Modifications are complete to the piping of the HVAC equipment serving the electric board rooms and the main control room.
5. Solenoids qualified for higher ambient temperatures are being installed on various dampers in the plant.
6. Hanger modifications continues.
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