ML20070A573

Monthly Operating Repts for Dec 1990 for Sequoyah Nuclear Plant Units 1 & 2

ML20070A573
Person / Time
Site:	Sequoyah
Issue date:	12/31/1990
From:	Hollomon T, Wallace E TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9101230222
Download: ML20070A573 (9)

Text

.

,U' s.

TENNESSEE VALLEY- AUTHORITY.

TSB Lookout Place Chattanooga,_ Tennessee, 37402-2801 January- 15, 1991-q LU.S.1 Nuclear Regulatory Commission ATTN Document-Control Desk =

Washington,:D.C. 20555

=Gentlement In the Matter of- ) Docket Nos. 50-327

. Tennessee._ValleyLAuthority

~

. ). 50-328

.SEQtJOYAH NUCLEAR PLANT _(SQN) - DECEMBER 1990 MONTHLY OPERATING REPORT  ;

EnclosedLis:.the-December 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,

-TENNESSEE VALLEY AUTHORITY 4~~-

E.-G. Wallace, Manager i Nuclear' Licensing and.

Regulatory Affairs

, Enclosures ->

.cc _(Enclosurt-)u Mr. ?J.1 N. iDonohew,L Project Manager - NRC Resident 1 Inspector U.S.; Nuclear-Regulatory Commission _Sequoyah Nuclear Plant OnoLWhite Flint,1 North 2600 Igou. Ferry Road-11555 Rockville: Pike Soddy _-Daisy,= Tennessee 37379 l Rockville,cMaryland 20852.

Regional' Administration- .

U.S. Nuclear. Regulatory, Commission 4 INP0: Records Center Institute +of Nuclear Power Operations ~0ffice of Inspection and Enforcement i

1100cCircle 75' Parkway, Suite 1500- Region II Atlanta,rGeorgia 30389 101 Marietta Street. NW, Suite 2900~

. Atlanta, Georgia 30.

=Mr.yTed Marston,-Director .

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

=PalocAlto, California 94304 Region II 101 Marietta Street, NW, Suite 2900--

Atlanta, Georgia 30323.

l I .

• 7 bhDbbk R

.y., yuyu 4

An Equal Opportunity Employer g I.

e m _, -- ,+J,e s+.-= k y 4.

9-TENNESSEE VALLEY AUTHORITY NUCLEAR POWER GROUP SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION DECEMBER 1990 UNIT 1 DOCKET NUMBER 50-327

-LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 i

I 1

i OPERAIIONAL

SUMMARY

DECEMBER 1990 UNIT 1 Unit-1 generated 860,290 megawatt hours (MW h ) (gross) electrical power during December, with a capacity factor of 97.74 percent. Unit 1 operated at approximately 100 percent reactor power level from the beginning of December until December 17, 1990, at 0755 Eastern standard time (EST). At this time, the " motor trip out" annunciator alarmed, and the unit operators observed that all three No. 3 heater drain tank pumps (HDTPs) had tripped simultaneously. Because of a resultant high level. the dump back valves f rom the No. 3 heater drain tank (HDT) to the condenser opened, initiating a turbine runback to approximately 76 percent power.

Further_ manual reduction of power to approximately 60 percent reactor power was performed by the operators to stabilize the secondary side of the plant.

Investigations determined that the apparent cause of the No. 3 HDTP trip was a result of the failure of the Low Level Switch, LS-6-104B. With the HDT being controlled at a high level dumping back to the condenser, the switch continued to remain open, which should have been indicative of a low level. Upon disassembly of the switch, the float was found full of water with two pin holes. Repairs were made, and Unit 1 was again operating at 100 percent reactor power level on December 18, 1990, at 1300 EST and continued to operate at approximately 100 percent reactor power level through the end of December.

UNIT 2 Unit 2 generated 822,300 MWh (gross) electrical power during December with a capacity factor of 93.43 percent. Unit 2 was_ operating at approximately 61 percent reactor power level on December 1. 1990, following start-up from a reactor trip that occurred on November 23, 1990. Unit 2 reached 100 percent reactor power level on December 6, 1990, at 2230 EST and continued to operate at approximately 100 percent through the end of December.

POWER-OPERATED RELIEF VALVES (PORVs) AND SAFETY VALVES

SUMMARY

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

- 0FFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES There were no changes to the ODCM during December.

l

. l

c.  ;

-.- l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT No. One DATE: 01-08-91 1

COMPLETED BY T. J. Hollomon TELEPHONE: (615) 843-7528 MONTH: ' DECEMBER 1990 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY. (MWe-Net) 1- 1132 17 820 2- 1136 18 1064 3 1134 19 1131 4 1132 20 1131 5 1133 21 1130

.6 1133 22 1131 7= 1134' 23 1131

-8 1133 24 1131 9 1132 25 1131 t 10- 1131 26 1132

. 11 1131 27 1131 12 1130 28 1128 13- '1130 29 1132

'14 1130 30 1133 15 1131 31 ____

1132

-16 1130

'4 g - -c -c.-:,----.-- .s-y, g=u g- r . , , , - -

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.- 50-328 UNIT No. Two DATE: 01-08 01 COMPLETED BY: T. J. Ito11omon TELEPHONE: (615) 843-7528 MONTH: DECEMBER-1990 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY ( MWe *' ' t ) DAY (MWe-Net) 1 777 17 1133 2 807 18 1131 3- 812 19 1131 4- 841 20 1130 5 987 21 1128 6 1040 .

22 1132 7 1138 23 1128

'8 1134 24 1120 9 1132 25 1133 10 1131 26 1133 y 11 1130 27 1132 12 1132 28 1124 13 1128 29 1131 14- 1132 30 1130 15 1130 31 1130

, 116 1132 4

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

. OPERAi!NG OATA REPORT DOCKET NO. .30-327 DATE Jan. B.1991 COMPLETED DY Udg.119mar t ,

TELEPHONE 11.11) 843-7526 OPERATING STATU$ __

l Notes l

1. Unit Name: _ Seoueyan Unit One

_ l l

2. Reporting Period: 2cied er 1990 l l

3. Licensed Thermal Power (HWt): 3411.0. l l

4. Nameplate Rating (Gross HWe): 1220.6 l l S. Design Electrical Rating.(Het MWe): 1149.0 l l

6. Maximum Dependable Capacity (Gross HWe)! ).1 n.0 l l

7. Maximum Dependable Capacity (het MWe); 1149.0 1 [

8. If %anges 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 MWe): N/A

10. Reasons for _ Restrictions, If Any: N/A this Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 0110 81 J05

12. Number of Hours Reactor Was Critical 744.00____ 6.H6.1. 49.072

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line . 711.0 6.406 L 39.096.0

15. Unit Reserve Shutdown Hours 0.0 _ 0

16. Gross Thermal Energy Generated (MWH) 2.510.66.1.0 20.950.147.0 127.286.0E7

17. Gross Electrical Energy Generated (HWH) J EO.200 7.095 & O 43.120.596 IB.-Net Electrical Energy Generated (MWH) 831.554 6.824.B47 41.296.976

19. Unit Service factor 100.0 73.1 46.9

20. Unit Availabili ty Factor - 100.0 73 1,, 46.9 l 21'. Unit Capacity Factor (Using MDC Net) 97.4 (L.L 43.2

22. Unit Capacity Factor (Using DER Net) _ 97.4 67.9 43.2 23 Unit Forced Outage Rate 0,0 7.L- 45.3 2% Shutdowns Scheduled Over Nent 6 Honths (Typo, Date, and Duration.nf Each):

25. If Shut Down At End Of Report Period. Estimated Date of Startup: N/A L

l 1 . - -

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

OPERATING DATA REPORT DOCKET H0. Se z8 CATC A L 1991 COMPTE *ED DY f. J. Hollomon TELEPHONE 1615) e43-752B OPERATIyG STATU$

l Notes l

1. -Unit Name: _Jengyah Unit Ing l l

2. Reporting Period: December 1990 l l

3. Licensed Ibermal nower (MWt): 3411.0 l l 4 Nameplate Rating (Gross MWe): 1220.6 l l

5. Design 'lectrical Rating (Het MWe): 1148.0 l l

6. . Maximum Dependable Capacity (Gross MWe): .1183.0 l l

.7. Maximum Dependable Capacity (Net MWe): 1148.0 l [

B. If Changes Occur in Capacity. Ratings (Items Number 3 Through 7) Since last Report, Give Reasons:

N/A

9. Power Level To Which Restricted, if Any (Het MWe): N/A

10. Reasons For Restrictions, If Any: t{/A _

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 8.760 75.265

12. Number of Hours Reactor Was Critical 744.0 6.940.8 40.471

13. Reactor Reserve Shutdown Hours 0 0 0-

14. Hours Generator On-Line 744.0 6.86LL 39.560.4

15. Unit Reserve Shutdown Hours 0.0 0 0

16. Gross Thermal Er.ergy Generated (MWH) 2.415.061.2 21.864.191.4 122.274.451

, Gross Electrical Energy Generated (HWH) 822.300 7.467.420 41.488.216

18. Net Electrical Energy Generated (MWH) 792.501 7.177.744 39.626.078

19. Unit Service Factor 100.0 78.4 52.6

20. Unit Availability factor 100.0 78.4 52.6

21. Unit Capacity Factor (Using MDC Net) 92.8 71.4 45.9

22. Unit Capacity Factor (Using DER Net) 92.8 71.4 45;9

. 23. - Unit forced Outage Rate 0.0 1.3 40.4

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25. If Shut Down At End Of Report Period, Estimated Oate of. Startup: N/A l

, 1

~

l 1

i  !

l- 1 l- . _ , - _ _ _ _ , _

e EECKET NO: 50-327 *

~

UNIT SHUIEDWNS AND POWED REDUCIIONS UNIT NAME: One .

DATE: 01/05/11 * ,

REPORT MONTH: December 1990 ' COMPLETED BY:T. .l. fiollomon .,

TELEPtiONE:(6151 643-7578 l Hethod of Licen-see Cause and Corrective Durati Shutting Down Event Systge Comppnent Action to No. Date Type) (Hours) . Reason2 Reactod Report No. Code Code Prevent Recurrence i

I 13 901217 f ~A 5 SJ LS On December 17, 1990, with Unit i aperating at near 100% power. the

" motor trip out" annunciator alarmed and the unit operators observed that all three #3 heater drain tank pumps (HDTP) had tripped simultaneously. Because of a resultant high level, the dump back valves f rom the #3 HDT to the condenser opened initiating a turbine runback to approximately 76 percent power.

Further manual redoction of power to approximately 60 percent reactor power was performed by the operators to stabilize the secondary side'of the plant.

Investigations revealed that the apparent cause of the #3 HOTP trip resulted from the failure of the Low Level Switch. LS-6-104E.

With the HOT being controlled at a high level dumping back to the condenser, the switch continued to remain open, which should have been indicative of a low level.

Upon disassembly of the switch, the float was found full of water with two pin holes. The float was replaced, and Unit I was again at 100 percent reattor power on December 18 1990, at

• 1300 (EST).

I F: Forced 2 Reason: #

3 Method: Exhibit G-Instructions r S: Scheduled A-Equipment failure (Explain) 1-Manual . fer Preparation of Data B-Maintenance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) file D-Regulatory Restruction 4-Eontinuation of Existing Outage (NUREG-1022)

E-Operator Iraining and License Examination 5-Reduction F-Administrative 9-Other G-Operational Error (Explain) SExhibit I-Same Source H-Other (Explain) i

c>

DOCKET NO: 50-323 .

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME: Two -

DATE: 01/08/91 '

REPORT HONTH: December 1990 . COMPLE1ED BY:T. J. Hollomon TELEPti0t4E:(615) 843-7528 ..

Method of Licensee Cause and Corrective Duration Shutting Down Event'. Systgm Comppnent Action to No. Date Type l (Hours) Reason2 Reactor 3 Report No. Code Code Prevent Recurrence 7 901123 F 54.65 G 3- 328/90017 Unit 2 was operating at approximately 61 percent reactor power level at the beginning of December, recovering from a reactor trip that occurred on November 23, 1990. Unit 2 reactor power level continued to increase and was again at 100 percent on December 6, 1990, at 2230 EST.

I:F forced 2 Reason: 3Hethod: d Exhibit G-Instructions 5: Scheduled A-Equipment failure (Explain) 1-Manual f or Preparation of Data B-Haintenance 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 Outage (NUREG-1022)

E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other G-Operational Error (Explain) 5 Exhibit I-Same Source H-Other (Explain)

=

,. r