ML20101E180

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Monthly Operating Repts for May 1992 for Sequoyah Nuclear Plant
ML20101E180
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 05/31/1992
From: Holloman T, Joshua Wilson
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9206230096
Download: ML20101E180 (10)
v • d • e


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Hl4 Tennessee Vaney AuttoJy Post OSce B"w 2iXR Soddy-Dasy_ Tenressee 37373 -

P J L Wilson v,ce rvescent seqwvan uwear Pian June !! 1992 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 l

! Gentlemen:

l In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PIANT (SQN) - MAY 1992 MONTHLY OPERATING REPORT Enclosed is the May 1992 Monthly Operating Report as required by SQN Technical Specificacion 6.9.1.10. .

If you have'any questions concerning this matter, please call M. A. Cooper at (615) 843-8924.

Sincerely, 5t L L. Wilson-Enclosure cc : - See page 2 i

9206230096 920531 .

PDR ,ADOCK' 05000327^

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, l U.S. Nuclear Regulatory Commission Page 2 June 15, 1992 cc (Enclosure):

INPO. Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30389 Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville~ Pike Rockville, Marylan' 09852 Mr. Ted Marston, Director- .

Electric Power Research Institute P.O. Box 10412 Palo Alto, California 94304 NRC Resident Inspector Sequoyah Nuclear Plant 2600:Igau Ferry Road Soddy-Daisy, Tennessee 37379 Regional Administration U.S. Nuclear Regulatory Commission Office-of-Inspection and Enforcement

-Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. - B. A. Wilson, Project Chief.

U.S. Nucleae Regulatory O mmission e Region II 101 Marietta Street, NW,-Suite 2900 Atlanta,- .argia 30323

-Mr. F.=Yost,- Director Research Services

--Utility Data Institute 1700 K Street, NW, Suite 400 Washington, D.C. 20006 s

F-TENNESSEE VALLEY AUTHORITY NUCLEAR IT6fER CROUP SEQUOYAH NUCLEAR PLANT

!!JNTHLY OPERATING RsPORT TO THE NUCLEAR REGUIATORY C019 FISSION IEL1192 UNIT 1 DOCKET NUMBER 50-327 l-LICENSE NIMBER DPR-77 UNIT 2 DOC 1El NUMBER 50-328-LICENSE NUMBER DPR-79 g .

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OPERATIONAL

SUMMARY

MAY 1992 UNII_1 i Unit 1 generated 693,240 megawatthours (MWh) (gross) electrical power during May, with a capacity factor of 80.2 percent. At the beginning of May Unit i remained in a forced outage for steam dump valve control circuitry repair and replacement.

.l On May 2, unit restart was initiated and reached 100 percent reactor power  !

level on May 5 at 0710 Eastern daylight time (EDT).

At 0401 EDT on May 16, with Unit 1 operating at 100 percent reactor power level, both No. 7 heater drain tank pumps (HDTPs) tripped simultaneously.

Operations' initiated a power level _ decrease because of loss of No. 7 HDTP flow and the expected low pressure heater string isolation. When the low pressure heaters isolated, Unit I was manually tripped as a-result of the transient.

On May 17, tulit restart was initiated, and 100 percent reactor power was reached on May 19. The unit continued to operate at near 100 percent power through the end of May.

UNII_2 The-Unit 2 Cycle 5 refueling outage ended on May 17, when Unit 2 was returned to service.. Unit 2 generated 285,730 MWh (gross) electrical power during May, with a capacity factor of 33.1 percent.

Unit 2 was taken'offline for_the scheduled turbine overspeed test on May 18 at 2122 EDT, and was returned to service on May 19 at 0518 EDT, upon completion of the turbine overspeed test.

Unit 2 reached 100 percent reactor power on May 27 at 2020 EDT, and continued I to operate at 100 percent power through the end of May.

EDER-QZEl%IED_ RELIEF VALVES AND_EAEETY VALVES

SUMMARY

r On May 16, Unit I was manually tripped af ter both No. 7 HDTPs tripped. The steam generator pressure before the reactor trip was constant at approximately 842 pounds per squara inch gauge-(psig). After trip initiation, steam generator pressure was approximately 1008 psig, which is approximately no-load setpoint. -Steam-generator pressure-operated relief valves (PORVs) did lift momentarily, with the Loop 2 PORV being the last to reseat. Technical r;ecification_and Final Safety Analysis Report requirements were not challenged.

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AVERACE IMILY UNIT POWER LEVEL DOCKET N0, 50-327 UNIT No. __Dne DATE: _Q4-DE_92 COMPLETED BY: I. J. Hollomon TELEPHONE: 1611)_Bit 3-1128 MONTH: _ MAL 119L AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (tfde-Ne t ) DAY (MWe-Net) 1 -16 17 -17 2 -16 18 360 3 12 19 1060 4 264 20 1125 5 1036 21 1129 6 1134 22 1127 7 1134 23 11.31_

8 1135 24 1132 9 1133__ _ 25 1132 _

10 1133 _ 26 1131_

11 1126 27 1131 12 1132 28 1128 13 1136 29 1115 14 L135 30 1132 15 -1135 31 1134 16 1Z0

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. _ _3D-328 UNIT No. __lgo DATE: _D6:08-92 COMPLETED BY: L___L__Ro.ll.Dmon TELEP110NE: Utl3.)_8f3-2328 t

MONTH: R Ll212_

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWm-Met) _ _ DAY (MWerNet) 1 -19 17 L4 2 -23 18 HL 3 _._ -2L 19 161 4 _21 20 2.uL 5 -12 21 _ 333 6 -9 22 740 7 -1L 23 SQ8 8 -16 24 938 9 -16 25 1087 10 -16 26 lab 9 i 11 -16 27 1Q93 12 -16 28 1113 13 -16 29 1116 i 14 -16 30 1125 15 -16 31 1123 16 -30

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-OPERATING DATA REPORT DOCKET NO. _50-327

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DATE _lui,e 8 m1992__._

COMPLETED BY 1, M ollDmon_,

TELEPHONE 16.15) 843-7528 OPERATING STATUS-l Notes l'

'1. Unit Name: . Sequoyah Unit One . _ _

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2. Reporting Period: May 1992 l l
3. Licensed Thermal Power (MWt): 3411.0 l l
4. Nameplate Rating (Gross MWo): _.]ZZO.6 l l
5. Design Electrical Rating (Net MWe): 1148.0 l l
6. Maximum Dependable Capacity (Gross HWe): _1162.0 l l

-7. Maximum Dependable Capacity (Net NWe): _1121 0 l {

8. If Changes Occur in Capacity Ratings.(Item Numbers 3 Through 7) Since Last Report, Give Reasons:
9. 'ower Level To Which Restricted, If Any (Het HWe): N/A 10.. Reasons for Restrictions, If Any: N/A This Month Yr-to-Date Cumulative
11. Hours in Repo -ting Peri .d 744 3.647 95.712 1

- 12.. Humber of Hours Reactor Was Critical 674 1 2.609.6 49.763.0

13. Reactor Reserve Shutdowr. Hours 0 0 0

.14. Hours Generator On-Line )7.2 . 2.765.5 48.636.J _

15, Unit Reserve- Shutdown Hours 0.0 0 0

16. Gross Thermal Energy Generated (MWH) 2.040.996.8 8.735.143.8 , 158.347.677

,17. Gross Electrical Energy Generated (tMi 693.240 3.001.188 53.668 661 ,_

18. Net Electrical Energy Generated (MWH) 663.449 .. _ 2.879.544 _ 51.444.278

.19. Unit Service factor - 85.6 75.8 __

50.8

'20. Unit Availability Factor 85.6 75.8 _ 50.8

21. Unit Capacity Factor (Using HDC Net) 79.5 JQd_ 47.9 E 22. Unit Capacity Factor (Using DER Net) 77.7 68.8 46.8 23.. Unit Forced Outage Rate 14.4- 24 2_ 40.7

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

25;-If Shut Down At End Of Report Period, Estimated Date of Startup:

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-OPERATING DATA REPORT DOCKET NO. J0-328 -

DATE h,p 8.1992 COMPLETED BY T. J. Hollomon TELEPHONE (615) 843-752S_._

QfLR/dih0JIAUll l Notes l

,1. . Unit Name: ._SeguG3Ah Unit Two l l

2. Reporting Period: May 1992 l l

- 3. Licensed Thermal Power (HWt): 1411.0 l l 4 Nameplate Rat *ag (Gross MWe): 1220.6 l l S. Design Electrical Rating (het MWe): 1148.0 l l

6. Maximum Dependable Capacity (Gross HWe): _116Zt0 l l

'7. Maximum Dependable Capacity (Net MWe): 1122.0 _ l l 8.- If.. Changes Occur in Capacity Ratings (I_ tem Numbers 3 inrough .7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net (1We): N/A
10. Reasons For Restrictions, If Any: N/A This Month Yr-to-Date Cumulative
11. Hours in Reporting Period 744 3.647 87.672
12. Number of Hours Reactor Was Critical 404.2 2.12L.Z_ 51.130
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours-Generator On-Line_ 345.6 2 050.1 50.Q93.3

'15. Unit Reserve Shutdown Hours 0.0 0 0 16.'Cr?ss Thermal Energy Generated (MWH) 870d08.2 _ 1 030.740.7 156.958.053 y 17. Gross Electrical Energy Generated (HWti) 285.730 2.047.996 .53.2 L ?87

18. Net Electrical Energy Generated (MWH) 266.462 _ 1.952.405 JDJo1;69 -

p 19. Unit Service Factor 46.5 SW_ _

57.1

-20. Unit Availability Factor 46.5 56.2 57.1

. 21. Unit Capacity Factor (Using MDC Net)- 31.9 47.7 51.7

22. Unit CapScity Factor (Using DER Net). 31.2 46.6_ 50.6
23. Unit Forced Outage Rate 0.0 2.1 35.1 24.; Shutdowns Scheduled Over Next 6 Months (fype, Date, and Duration of Tach):

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25. If Shut Down At End Of Report Period, Estir.ated Date of Startup:

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DOCKET NO: 50-327 '.

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UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME: One DATE: 06/08/92 ,,

REPORT HONTH:. MAY 1992 COMPLETED BY:T. J. Hollomon TELEPHONE:1615) 843-7528 --

Method of. Licensee Cause and Corrective Durati on Shutting Down Event System Action to Compgnent No. Date Tppe l (Hou rs) - Reason 2'

Reactor 3 Report No. Code 4

Code Prevent Recurrence '

5 920428 F 66.7 A 4 327/92010 FK RLY 327/92011 SB PIC Unit I remained in a forced outage for steam dump valve control circuitry repair and .

replacement. Unit I tied online on 5/3/92 and reached 100 percent power on 5/5/92.

6 920516 F 40.1 A 2 327/92012. 06 LIC. The Unit I reactor was manually i tripped because of . loss of the '

No. 7 heater drain tank pumps, resulting from low pressure heater string isolation. When the low ,

pressure heaters isolated. Unit 1 -r was manually tripped. Ine'cause l of the transient was the failure of the No. 7 heater drain tank level control valve positioner. '

The positioner was repaired and returned to service.

Unit I was taken critical again on 5/17/92 at 0724 Eastern daylight '

time (EDT), and was tied online at 2013 EDT that fsee day. Unit I reached 100 percent reactor power on 5/19/92. j l.

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I:F Forced 2 3 #

Reason: Hethod: Exhibit G-Instructions  ;

S: Scheduled A J+2irment Failure (Explain) 1-Manual for Preparation of Data i B-Naintenan e 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-Operat < onal Error (Explain) S Exhibit I-Same Source H-Other (Explain) i i

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. DOCKET NO: '50-329' .g UNIT SHUTDOWNS AND POWER REDUCTIONS. UNIT NAME: Two ..

DATE:- 06/08/92 REPORT HONTH: May 1992' COMPLETED BY:T. J. Hollomon W ^

TELEPHONE:f 6151 843-752!! .-

Method of Licensee Cause and Corrective

. Duration Shutting Down Event System- Compgnent Action to

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l 2 Reactor3 No. l Date. Type (Hours) Reason Report No. Code Code Prevent Recurrence

2 920313 5 390.5 'C 4 N/A N/A N/A' The Unit'2 Cycle 5 r= fueling  !

outage ended on 5/17/92 when the [

generator was tied online at' 0628 Eastern daylight time (EDT). .

3 920518 5 7.9 B- 9 N/A N/A N/A The Unit'2 generator was taken off-line at 2122 EDT on .*'18/?2 for a scheduled turbine test, following completion of the Unit 2 Cycle 5 ~

) refueling outage. The Unit 2 gen-5 erator was again tied to the grid on 5/19/92 at 0518 EDT, and Unit 2 reached 100 percent reactor power ,

level at 2020 EDT on 5/27/92.- t i

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I I:F Forced 2 Reason: 3Method:

.4Exhibit 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 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) t

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