ML20065S190

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Monthly Operating Repts for Nov 1990 for Sequoyah Nuclear Plant Units 1 & 2
ML20065S190
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/30/1990
From: Holloman T, Wallace E
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9012200138
Download: ML20065S190 (9)
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,, ' ! '~ - l TENNESCEE VALLEY AUTHORITY 1-4 F

$B Lookout Place Chattanooga, Tennessee 37402-2801 '

3 December 17, 1990 i

U.S. Nuclear. Regulatory Commission ATTN Document Control Desk Washington, D.C. 20555 Gentlement ,

u

-In the Matter of _ ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - NOVEMBER 1990 MONTHLY OPERATING REPORT i

' Enclosed is the November 1990 Monthly Operating Report as required by SQN Technical Specification 6.9.1.10.  !

If you have any questions concerning-this matter, please call M. A. Cooper at (615)-843-8422.  ;

Very truly yours, -

TENNES,SEE VALLEY AUTHORITY  !

07t-

. G. Wallace, Manager Nuclear Licensing and

~ Regulatory Affairs ,

Enclosure >

cc-(Enclosure): . .

Mr. 'J. N. -Donohew, Project Manager NRC Resident Inspector U.S.; Nuclear Regulatory Commission- Sequoyah Nuclear Plant ,

One White Flint,. North 2600 Igou Ferry Road -

11555 Rockv111e' Pike. Soddy-Daisy. Tennessee 37379

-t Regional Administration .

..INPO Records Center- U.S. Nuclear Regulatory Commission; Institute of Nuclear Power Operations Office of Inspection and Enforcement-1100 circle 75 Parkway, Suite 1500- Region II.

~

Atlanta, Georgia 30389 101 Marietta Street,-NW, Suite 2900 Atlanta, Georgia 30323  :

--Mr.-Ted Marston,-Director .

Electric Power.Research Institute- Mr. B. A. Wilson, Project Chief P.O. Box 10412 U.S. Nuclear Regulatory Commission; -

-Palo' Alto, California- 94304- Region II' .

.101 Marietta Street NW, Suite 2900' Atlanta, Georgia 30323 901220013e 901130 PDR ADOCK0500g7

- An Equal Opportunity Employer f_/J{ l .

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TENNESSEE VALLEY AUTHORITY NUCLEAR POWER GROUP SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION NOVEMBER 1990 UNIT 1 DOCKET NUMBER $?-327 LICENSE NUMBER DPR-7/

k UNIT 2 ,

DOCKET NUMBER 50-328 f

LICENSE NUMBER DPR-79 5

l -

OPERAIl0NAL S M Y NOVEMBER 1990 UNII1 Unit 1 generated 828,860 megawatthours (MW h ) (gross) electrical power during November, with a capacity factor of 97.31 percent. Unit 1 operated at 100 percent reactor power level from the beginning of November until November 15, 1990. On November 15, 1990, at 0232 Eastern standard time (EST) Preferred Power Board 1 supply fuse opened, deenergizing the board. At approximately 0435 EST, a licensed operator placed the main feedwater pump (MFP) 1A oil pump handswitch in the position required to clear the alarm. Unexpectedly, the oil pump tripped, resulting in a trip of the MFP. The main turbine ran back automatically. The unit was stabilized at approximately 60 percent reactor power level while the incident was investigated. The cause of the event has been attributed to a faulty relay.

The relay was replaced and Unit I was returned to 100 percent reactor power level on November 16, 1990, at 1205 EST, and continued to operate at 100 percent through the end of November.

UNil2 Unit 2 generated 56,620 MWh (gross) electrical power for November, with a capacity factor of 6.65 percent. Unit 2 began November in Mode 5 with Unit 2 Cycle 4 refueling outage still in process.- On November 3, 1990, at 0647 EST, Unit 2 entered Mode 4. On November 4, 1990, problems were discovered with the reactor coolant pump (RCP) 2 No. 1 seal leakege. At 1555 EST on November 5, 1990, Unit 2 cooldown was initiated, and the unit entered Mode 5 at 1910 EST. The No. I seal was replaced and Unit 2 entered Mode 4 on November 7, 1990, at 2146 EST and entered Mode 3 on November 8, 1990, at 0500 EST. On November 12, 1990, at 1730 EST, Unit 2 went critical. After experiencing problems with RCP 1 leakoff, Unit 2 entered Mode 3 on November 13, 1990, at 0507 EST, entered Mode 4 at 0930 EST, and entered Mode 5 at 1258 EST. The No. 1 seal was replaced and Unit 2 heatup was again initiated on November 16, 1990, at 0841 EST. Unit 2 entered Mode 4 at 1630 EST and entered Mode 3 at 2133 EST. On November 20, 1990, at 1232 EST, Unit 2 was again critical. Unit 2 entered Mode 1 on November 21, 1990, at 1948 EST and on November 22, 1990, at 0241 EST, Unit 2 tied online. This marked the end of the Unit 2 Cycle 4 refueling outage.

Unit 2 was taken offline on November 22, 1990, at 1206 EST, for the turbine overspeed test and was back online at 1333 EST.

On November 23, 1990, with Unit 2 at approximately 30 percent reactor power level.

Unit 2 tripped at 0432 EST, on low pressurizer pressure and entered Mode 3. The trip occurred as a result of the loss of an RCP caused from deenergization of its unit board and subsequent operator actions. The cause of the unit board deenergization resulted from a possible electrical switchgear malfunction of the 62-224 relay. Relay testing was conducted and the relay returned to service. The unit was taken critical on November 24, 1990, at 2151 EST, and entered Mode 1 on November 25, 1990, at 0621 EST. Unit 2 tied online again on November 25, 1990, at 1111 EST. Unit 2 was operating at approximately 61 percent reactor power level at the end of November.

POWER-OPERATED RELIEF VALVES (PORVs) AND SAFETY VALVES

SUMMARY

There were no challenges to PORVs or safety valves in November.

l OFFSITE DOSE CALCULATION MANUAL (0DCM) CHANGES l There were no changes to the ODCM during November.

'. i AVERAGE DAILY UNIT POWER LEVEL 1

l DOCKET NO. 50-327 UNIT No. One DATE: _J2-06-90 COMPLETED BY: T. J. Ho11omon TELEPHONE: (615) 843-7528 MONTH: NOVEMBER 1990 I AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net) 1 1127 17 1143 2 __

1127 18 1147 .

3 1127 19 1137 4 1128 20 1128 5 1122 21 -

1129 6 1129 22 1134 __

7 1128 23- 1132 8 1127- 24 1131 9 1128 25 1133 10 1125 26 1132 11 1126 27 1133 12 1125 28 1132 13 1125 29 1131 14 1126 30 1132 15 760 31 N/A 16 1027 l

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

. '. l AVERACE DAILY UNIT POWER LEVEL l

DOCKET NO. 50-328 UNIT No. Two DATE: _12-06-90 i

COMPLETED BY: T. J. Hollomon TELEPHONE: (615) 843-7528 MONTH: NOVEMBER 1990 I

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net) 1 -4 17 -8 2 -5 13 -8 3 -4 19 - 10 4 -8 20 - 10 5 -7 21 - 10 6 -4 22 123 7 -6 23 39 ___

8- -7 24 - 10 9 - 10 25 70 10 -8 26 _

233 11 - 10 27 235 12 -8 28 231 13 -7 29 257 14 -5 30 525 15 -9 31 N/A 16 -7

OPERAi!NG DATA REPORT DOCKET NO.11-327 DATE Dec. 7. 1990 COMPLETED BY T. 1. Hol,l omon TELEPHONE (616) 843 7528 OPERATING STATU$

l Notes l 1 Unit Name: ___$eauoyah Unit One l l

2. Reporting Period: November 1990 l l
3. Licensed thermal Power (HWt): _3411.0 l l 4 Nameplate Rating (Gross HWe): 1220.6 l l

$. Design Electrical Rating (Net HWe): _1148.0 l l

6. Maximum Dependable Capacity (Gross HWe): J_18 3. 0 l l
7. Maximum Dependable Capacity (Net HW6): 1148.0 l l
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) $lnce Last Report. Give Reasons j N/A
9. Power Level to Which Restricted, If Any (Net HWe): N/A
10. Reasons For Restrictions, If Any: N/A l This Month Yr-to-Date Cumulative
11. Hours in Reporting Period 720 8.016 82.561
12. Number of Hours Reactor Was Critical 720.00 S.832.8 39.328
13. Reactor Reserve Shutdown Hours 0 ._ 0 0
14. Hours Generator On-Line 720.0 5.662.6 38.352.0
15. Unit Reserve Shutdown Hours 0.0 0 0
16. Gross Thermal Energy Generated (HWH) 2.420.581.9 _ 18.439.485.1 124.775.405
17. Gross Electrical Energy Generated (HWH) 828.B60 6.236.540 42.260.296 q
18. Net _ Electrical Energy Generated (HWH) . 792.501 5.993.293 40.465.322 _ _  !
19. Unit Service factor .00.0 70.6 46.5
20. Unit Availability Factor 100.0 70 6 46.5
21. Unit Capacity Factor (Using HDC Net) 95.9 65.1 42.7
22. Unit Capacity Factor (Using DER Net) 95.9 65.1 42.7
23. Unit Forced Outage Rate 0.0 R.2_ 45.8
24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
25. If Shut Down At End Of Report Period. Estimated Date of $tartup: N/A

OPERAi!NG DATA REPORT DOCKET NO. .50-32B DATE _Dec. 7. 1990 COMPLETED BY T. 1. HollomQa_.

TELEPHONE (6151 843-7E2B OPERATIN3 $TATU$

l Notes l

1. Unit Name __$equgvah Unit Two l l
2. Reporting Period ___ November 1990 l l
3. Licensed Thermal Power (HWt): _3411.0 l l 4 Nameplate Rating (Gross HWe): .1220.6 l l
5. Design Electrical Rating (Net HWe)t __1149.0 l l
6. Maximum Dependable Capacity (Gross HWe): 1183.0 l l
7. Maximum Dependable Capacity (Net HWe): .1148.0 l l
8. If Changes occur in Capacity Ratings (!tems Number 3 Through 7) Since Last Report. Give Reasons:

N/A

9. Power Level to Which Restricted, if Any (Net HWe): N/A 10._ Reasons For Restrictions, If Any: N/A This Month Yr-to-Date Cumulative
11. Hours in Reporting Period 720 8.016 74.521
12. Number of Hours Reactor Was Critical 221.8 6.196.8- 39.727 j
13. Reactor Reserve Shutdown Hours 0 0 0
14. flours Generator On-Line 157.2 6.120.6 3L816.4._
15. Unit Reserve Shutdown Hours 0.0 0 0
16. Gross Thermal Energy Generated (HWH) _ 180.336.0 19.449.130 2_ 119.859.390
17. Gross Electrical Energy Generated (HWH) 56.620 6. 64 5.12(L_,,, ._43 & 5.916 i
18. Net Electrical Energy Generated (HWil) 48.281 6.385.243 39.833.577 I
19. Unit Service Factor 21.8 7 6 , 4_,, 52.1
20. Unit Availability factor 21.B_ _ /6.4 52.1
21. Unit Capacity Factor (Using HDC Net) 5.8 6LA,, 45.4
22. Unit Capacity f actor (Using DER Net) 5.8 69.4 45.4
23. Unit Forced Outage Rate 25.8 1.5 40.9
24. $hutdowns $cheduled Over Next 6 Honths (Type. Date, and Duration of Each):
25. If Shut Down At End Of Report Period. Estimated Date of Startup N/A 1

DOCKET NO: 50-327

  • UNIT SHUTDOWNS Ato POWER DEDUCTIONS UNIT NAME: One DATE:JJLDZ/90 REPORT m NTH: tscve=ber 1990 COMptETED BY:Tm J J llomon TELEPHONE:(6151 843-7523 . .

Method of Licensee Catase and Corrective Duration shutting Down Event Systp C q eent Action to No. Date Type (Hours) Reason Reactor3 _Eeport No. Code Code Prevent Recurrence s 12 901115 F A 5 327/90030 BA RLY November 15.1990 at 0232 (EST)

Preferred Power Board I supply fuse opened, de-energizing the board. At appronimately 0435 (EST), a licensed operator placed the MTP 1A eil pump handswitch in the positi s required to clear the esara.

Unenpectedly, the oil pump i tripped, resulting 'a a trip of the MFP. The riai. turbine ran back automatitA ly. The unit was stabilized i*. approminately 60 percera reactor power level while the incident was investigated. The cause of the event has been attributed to a faulty mechanical latch on the operating coil of the relay for ,

the oil pump. The relay was replaced. Unit I was operating  ;

at 100 percent reactor power level again on November 16. 1990, at 1205 EST. and continued to operate at 100 percent thro gh the end of November.

I:F Forced 2 Reason: 3 Method: 4 Erteb R G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Maneal for Preparation of Data B-Maintenance or Test 2-Manual Scr.as Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restru.: ion 4-Continuation of Existing Outage (NUREG-1022)

E-Operator Trai6eing and License Examination 5-Reduction F-Administrative 9-Other G-Cperational Error (Esplain) SEnhibit I-Same Seurte t$-Other (Emplain)

i.-

l DOCKET NO: 50-328  ?

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT IMME: Twe '"'

. DATE: I I/D U30__

REPORT MONTH: 1sovember 1990 COMPLETED BY: IJmoU.omon H .

  • TELEPHONE:(615) 843-75ZS Method of Licensee Cause and Corrective

.! D:rration Shutting Do-n Event Systy C at Action to No. Date Type I (Hours) Reason 2 Reactor 3 - Report No. Code Cod Prevent Recurrence 5 900908 5 1800.' C 1 Unit 2 Cycle 4 (UZC4) refueling outage continued until

, November 22.1990, at 0241 EST.

when Unit 2 tied online. This marked the end of the U2C4 refueling out,ge.

6 901122 _5 1.5 8. 1 Unit 2 was taken offline on November 22. 1990, at 1206 EST, 4 for the turbine overspeed test and was back online at 1333 EST.

7 901123 F 54.65 G 3 328/90017 On Noweeber 23, 1990. Unit 2 tripped at 0432 EST on low-pressurizer pressere and entered Mode 3. The trip occurred es a result of the loss of an RCP caused by deenergiration of its unit board and subsequent opera-ter actions. The cause of the deenergiration of the wait board was a possible electrical switchgear malf unction of the 62-224 relay. The relay was tested and returned to service.

Operational personnel involved have received additionai train-ing. Unit 2 was again critical

, on November 24. 1990, at i 2151 EST, and entered Mode 1 on November 25, 1990, at 0621 ESI.

Unit 2 tied enline again om Nove=ber 25. 1990. at lill EST.

Unit 2 was operating at approximately 61 percent reactor power level at the end of Noventrer.

I: Forced 2 Reason: 3Method: 4 F Exhibit G-Instructions 1

5: Sc.heduled .A-Equipment Failure (Emplain) 1-Manual for Preparation of Data l B-Maintenance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restruction 4-Continuation of Existing Octage (NUREG-10ZZ)

E-Operator Training and License Emanination- 5-Reduction i F-Administrative 9-Other i G-Operational Error (Emplain) S Exhibit I-Same Source f+.0ther (Emplain) 4

. _ . _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ = _ _ _ - _ .

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