ML20084U770

Monthly Operating Repts for Mar 1991 for Sequoyah 1 & 2

ML20084U770
Person / Time
Site:	Sequoyah
Issue date:	03/31/1991
From:	Hollomon T, Wallace E TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9104220288
Download: ML20084U770 (11)

Text

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k Tenressee Wey Aumdy 1101 Manet Spect C%ttanasa Tennessee 3bO2 April 15, 1991 U.S. Nuclear Regulatory Cor:unission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-323 SEQL'OYAH NUCLEAR PLANT (SQN) - MARCil 1991 MONTilLY OPERATING REPORT Enclosed is the March 1991 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 t,ruly yours.

TENNESSEE VALLEY AUTHORITY

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,;/E.G.Wallace,knager a Nuclear Licensing and Regulatory Affairs Euclosure cc: See page 2 9104220288 910331 PDR ADOCK 05000327 R pop g l

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2 U.S. Nuclear Regulatory Commission April 15, 1991 cc (Enclosure):

Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 INPO Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, Georgia 30389 Mr. Ted Marston, Director Electric Power Research Institute P.O. Bcx 10412 Palo Alto, California 94304 NRO Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy Tennessee 37379 Regional Administration U.S. Nuclear Regulatory Commission Office of Inapection and Enforcement Region II 101 Marietta Street, NW, Suite 2900 .

Atlanta, Georgia 30323 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Fred Yost, Director, Research Services Utility Data Institute 1700 K Street, NW, Suite 400 Washington, D.C. 20006

IENSSEEVAllEYAUIB0RIIY ELEARPOWERGROUP SEQU0DJ1 ELEAR PLGI MONIHlYOPERATINGREPORI I0IHE ELEAR REGULAIORY C0)DilSSION MARCH 1991 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79

OPERATIONAL

SUMMARY

MARCH 1991 UNIT 1 Unit 1 generated 854,260 MWh (gross) electrical power during March, with a capacity factor of 98.8 percent. Unit I was operating at approximately ll( 99 percent reactor thermal power at the beginning of the month with a loss of efficiency resulting from the loss of No. 1 preferred inverter that caused the moisture separator reheater (MSR) valves to close. On March 1, 1991, at 0005 Eastern standard time (EST), the MSRs were manually placed back in service.

Unit 1 was at 100 percent reactor power level at 0746 EST on March 1, 1991.

On March 26, 1991, at 1326 EST, with Unit 1 operating at 100 percent reactor power, the No. I reactor coolant pump (RCP) oil reservoir high/ low alarm came in. Operations began monitoring the thrust bearing temperature and upper radial bearing temperature. Westinghouse Electric Corporation was contacted and recommended that the pump be shut down if either the thrust bearing temperature or upper radial bearing temperature increased 5 dea rces. On March 28, 1991, at 1017 EST, a load decrease was initiated for the inspection of the No. 1 RCP oil leak. Unit i reactor power was decreased to approximately 24 percent to facilitate as low as reasonably achievable (ALARA) for the containment entry. Two containment entries were made. The first entry found that the oil level was approximately one inch below normal and that a small quantity of visible oil was primarily in the vicinity of the bearing lift ayatem, which is used only during plant RCP startup and RCP shutdown. The second entry was made to add oil and clean noted standing oil to the extent possible taking into consideration ALARA.

On March 28, 1991, at 2320 EST, Unit 1 power increase was initiated. Unit i reached 99 percent reactor power on March 29, 1991, at 1555 EST. At 2145 EST, a power reduction was initiated to allow Operations to remove the No. 3 heater drain tank -(HDT) pump f rom service so that the 3C auxiliary oil pump could be manually stopped. Reduction in power to 80 percent ensured that a balance-of-plant runback did not occur when the No. 3 HDT pwnp was removed from service. Unit I was returned to 100 percent reactor power on March 30, 1991, at 0543 EST, and continued to operate at 100 percent through the end of the month.

UNIT 2 Unit 2 generated 866:260 MWh (gross) electrical power during March, with a capacity factor of 100.2 percent. Unit 2 was operating at approximately 100 percent reactor power on March 3, 1991, at 0143 EST, when the load dispatch requested a reduction of 100 >Ne. At 0245 EST, the load dispatch requested a further reduction of 100 MWo. At 0313 EST, load dispatch requested another reduction of 100 MWe, reducing power on Unit 2 to 876 MWe.

At 0437 EST, Unit 2 was operating at approximately 73 percent reactor power, producing 880 MWe, At 0544 EST, the load dispatch notified Operations to begin load increase to 100 percent reactor power. At 1055 EST, Unit 2 was again operating at 100 percent reactor power.

Unit 2 continued to opettte at approximately 100 percent reactor power level through the end of FMrch.

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k POWER OPERATED RELIEF VALVES (PORV) AND SAFETY VALVES SL7 MARY There were no challenges to PORVs or safety valves in March, OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES There were no changes to the ODCM during March.

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4 AVERAGEDAILYUNITPOWERLEVEL DOCKET NO. 50-327 UNIT No. One DATE: 04-09-91 COMPLETED BY1 T. J. Hollomon TELEPHONE: 1615) 843-7528 MONTH: MARCH 1991 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net) 1 1136 17 1135 2 1137 18 1136 3 1136 19 1135 4 1136 20 1134 5 1135 21 1135 6 1135 22 1137 7 1135 23 1137 8 1135 24 1136 9 1135 25 1137 10 1136 26 1137 11 1129 27 1138 12 1136 28 770 13 1136 29 749 14 1113 30 1107 15 1134 31 1140 16 1135

S AVERAGE dally ElI POWER LEVEL DOCKET NO. 50-328 UNIT No. Two DATE: 04-09-91 COMPLETED BY: T. J. Ho11omon TELEP110NE: (615) 843-7528 MONTH: MARCH 1991 AVERACE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net) 1 1132 17 1130 2 1133 18 1130 3 1050 19 L129 4 1114 20 1129 5 1122 21 1129 6 1126 22 1129 7 1127 23 1129 8 1126 24 1128 9 1128 25 1127 10 1127 26 1129 11 1128 27 1128 12 1131 28 1128 13 1132 29 1128 14 1129 30 1128 15 1130 31 1129 16 1131

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OPERATING DATA REPORT DOCKET NO. _10-327 DATE Aar. 9. 1991 COMPLETED BY T. 1. Hollomon TELEPHONE f615) 843-7528 OPERA *ING STATUS l Notes l 1, Unit Name: Seauovah Unit One l l

-2. Reporting Period: March 1991 l l

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

4. --Nameplate Rating (Gross MWe): 1220.6 l l S. Design Electrical Rating (Net NWe): 1148.0 l l

6. Maximum Dependable Capacity (Gross MWe): 1162.0 l l

- 7. Maximum Dependable Capacity (Not MWe): 1122.0 l l

8. If Changes Occur in Capacity Ratings (!tems Number 3 Through 7) Since Last Report. Give Reasons:

- 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 2.160 85.465

12. Number of Hours Reactor Was Critical 744.00 2.029.3 42.101

--13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 744.0 2.010.3 41.106.3

15. Unit Reserve Shutdown Hours 0.0 0 0

. :16. Gross, Thermal Energy Generated. (MWH) 2.504.521.5 6.758.362.6 134.044.430

17. Gross Electrical Energy Generated (MWH)- 854.260 2.311.390 _._- _ 45.431.026

18. Net _ Electrical Energy Generated (MWH) 825.887- 2.228.943 43.525.819

19. Unit Service factor 100.0 -93.1 48.1

20. Unit Availability Factor- 100.0 93.1 48.1 21.-Unit Capacity Factor (Using MOC Net) . 98.8 92.0 45.4 22.. Unit Capacity factor (Using DER Net): 96.7 89.9 44.4 23' Unit forced Outage Rate

. 0.0 6.9 44.2

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

-25. If Shut Down At End Of Report Period, Estimated Date of Startup: 7:/A l

OPERATING DATA RFPORT DOCKET NO. 50-328 OATE Ao r. 9. 1991 COMPLETED BY T. J. Hollomon TELEPHONE (6151 843-752fL., ,

OPERATING STATUS l Notes l

1. Unit Name: Secuovah Unit Two l l

2. Reporting Period: March 1991 l ]-

3. . Licensed Thermal. Power (Wt): 3411.0 l l 4 Nameplate Rating (Gross MWe): 1220.6 l l

5. Design Electrical Rating (Net MWe): 1148.0 l l

6. Maximum Dependable Capacity (Gross MWe): 1162.0 l l

7. Maximum Dependable Capacity (Net MWe): 1122.0 l l'

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7; Since tast Report. Give Reasons:

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 '2.160 77.425

12. Number of Hours Reactor Was-Critical 744.0 2.160.0 42.631

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours . Generator On-Line 744.0 2.123.0- 4LgE

15. Unit Reserve Shutdown Hours 0.0 0 0

16. Gross Thermal Energy Generated iMWH) 2.525.808.9 7.129.999.3 129.404.450

17. Gross Electrical Energy Generated (SH) 866.260 2.441.480 _43.929.696

18. Het Electrical Energy Generated (MWH) 835.594 2.355.456 41.981.534

~ 19. Unit Service factor 100.0 98.3 53.8

20. Unit Availability factor 100.0 98.3 _ 53.8

21. Unit Capacity factor (Using MDC Net) 100.2 97.2 48.3-

' 22. Unit Capacity Factor (Using DER Net) 97.9 95.0 47.2

23. Unit Forced Outage Rate 0.0 1.7 33.2

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

25. If Shut _Down- At End Of Report period, Estimated Date of Startup: N/A ~

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DOCKLT t4: 50-321 - ,

UNIT IM 5 : Qne UNIT SHulLsNS AND Powf R ktDUCTIONS DATE: 04E2/2 L___

COMPT [1ED BY: L_) m Ha]Iomsn ,

REPORT M0!JIH:_&nt 19M TELEPHONE:f615) 841-75Z3 9 Licensee Cause and Corrective Method of Action to Duration Shutting.Down Event Systgm Compgnent Code Prevent Recurrence Date lype 3 (Hours) Reason2 Reactor3 Report No. Code No.

$ AS P At 1011 LST. a load decrease 3 910328 f 6 was initiated for inspection and repair of the No. I RCP which had on oil reservoir high/ low alarm (ome in. tJnit I reactor power level was decreased approximately 24 percent to facilitate ALARA f or the containment er.try. Two containment entries were made.

The first entry identified that the oil level was approaimately one inch below normol. The second entry was made to add oil.

At 2320 ESI. Unit I power increase was initaated. Power was held at 45 percent for oppro=i-mately four hours while repairs were completed on the IB Mfp 1B1 main oil pump relay 8681. Unit i r eathed 99 percent reottor pu-er level on March 29 1991 at 1555 EST.

At 2145 LSI, a po-er reducteun 4 910329 I f 5 was initiated to allo- Operations to remove the tao. 3 HDT pump from servi (e so that the 3C oumiliary oil pump (ould be manually stopped. Redu-(tion in power t o 80 percent ensured thot a balance-of-plent runba(k dsd not occur when the No. 3 HDI puop was removed from servete.

Unit I was returned to !OO perc ent reactor power on March 30, 1991. at 0543 ESI.

and (0ntinued to operate at 100 percent through the end of the month.

I 2 Heason: 3 Method: 4tahibit G-Instructions f: for(ed 1-Manuol for Preparation of Data 5: Scheduled A-Equipment failure (Explain) Entry sheets for Licensee j B-Maintenance or Test 2-Manual $(ram Event Report (LER) file C-Refueling 3-Automatic Scram D-Regulatory Restruction 4-Continuation of Esisting Outage (NUREG-1022)

E-Operator training and License Examination S-Reduction I-Administrative 9-Ot he r SZ ,hibit I-Soe.e Source G-Operational Error (Explain)

H-Other (Emplain)

DOCKE1 t40: SQ.3?3 UNIT SHUIDowtas AND power ktDUCTIONS UNIT Ntd : Jwo DAl[: 04/WJ/31_ .

ktPORI NONIH: ftdrth 3 y1 t.OMPstitD BY:L_J Jollerren 1EiETHOnE:&13) 843-73?]

Method of L it en3cc Cause and Corsettive A<. tron to Duration Shutting Down twent Systy Com2ppnent Code prevent Returrevue ho. Date Typc I (Hours) Re<non 2 Reactor 3 keport feu. Code At 0113 EST. the load dispa*th 2 910303 f f 5 requested a reductso.i of 100 t%e.

At 0245 ISI, the load dispatch requested a furtiver redo (tion of 100 t%e. At J313 ESI. the lowd dispatc.h reques t ed anut.t.cr reduction of 100 MWe, reducinq po w er on Unit 2 to 87t.the. At 0437 EST, Unit 7 i.as operating dt approminately 73 per(ent reactor power level, produtiny 680 twe. At 0544 (SI. the load dispatch notified Operatioris to begin load increase to 100 penent rea(tor power. At 1055 L5I.

Unit 2 was again operating at 100 percent power.

l 2 Krason: 3Hethud: f .h its e t C.-leist ruc t ions I

f: for(ed s-Hanual sur Preparation of Data i 5: Scheduled A-fquipment f ailure (L, plain; intry sheets for License (* l B-Haisitenarice> or lest 2-Manual 5trem 3-Autonutic Strom E ver.t Report (I t N) f ile C-ketueling ( NUR t(.,- 1022) 4-Continuation of taisting Outage D-Regulatory Restruction t-Operator Training and i(ense f xamination 5-Weduction F-Administrative 9-Other ,

'tahibit I-54av Source G-Operational E rror (t, plain) it-Other (E xplain) l