ML20059A001

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

ML20059A001
Person / Time
Site:	Sequoyah
Issue date:	07/31/1990
From:	Hollomon T, Wallace E TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9008220085
Download: ML20059A001 (9)

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.1- . TENNESSEE VALLEY AUTHORITY

.. SN 1578 Lookout Place-Chattanooga, Tennessee. 37402-2801 .

August 15. 1990

• U.S. Nuclear' Regulatory Commission i ATTN: Document Control-Desk' Washington, D.C.- 20555. _

t Gentlemen: )

In the Matter of )' Docket Nos. 50-327--

Tennessee Valley. Authority  ;) 50-328' SEQUOYAH NUCLEAR PLANT (SQN) --JULY 1990 MONTHLY OPERATING REPORT:

Enclosed is the July 1990 Monthly Operating Roport as required by SQN Technical Specification 6.9.1.10.

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If:you have any questions concerning this ' matter, pier.se call M. A. Cooper at-(515)'843-6422.

Very truly yours, TENNESSES' VALLEY AUTHORITY' a

f$er"'"unussa E. G.-Wallace. Manager Nuclear Licensing and Regulatory Affairs Enclosure '

cc (Enclosure):

INPO Records Center NRC Resident Inspector-Institute of Nuclear Power Operations Sequoyah Nuclear Plant i

-1100 circle 75 Parkway, Suite 1500 2600 Igou Ferry Road, L Atlanta,. Georgia 30389 Soddy-Daisy, Tennessee 37379 Mr. J. N. Donohew Project Manager iRegional Administration -

U.S. Nuclear. Regulatory Commission U.S., Nuclear Regulat'ory Commission One White Flint, North . Office.of' Inspection andtEnforcement 1 11555 Rockville Pike Region II Rockville, Maryland 20852 101 Marietta Streeta NW, Suite' 2900 1Atidnta, GeoEgia 30323 .

Mr. B. D. Liaw.-Director TVA Projects. Division. Mr. B. ^.-Wilson, Project Chief One White Flint, North U.S. " ,..ar. Regulatory Commission I 11555 Rockville-Pike ' Region'. II Rockville, Maryland 20852 J101 Marietta Street NW,' Suite-2900

' Atlanta', Georgis 30323. j Mr. Ted Marston, Director Electric Power Research Institute.

P.O. Box-10412 Palo~ Alto, California 94304 003220083 900731 "

DR ADOCK 050'<0327 R PDC .

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j An Equal Opportunity Employer . -

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. TENNESSEE. VALLEY AUTHORITY NUCLEAR POWERIGROUP i SEQUOYAH NUCLEAR' PLANT .

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MONTHLY OPERATING REPORT- l l

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- .TO THE-NUCLEAR. REGULATORY COMMISSION g

JULY,1990 UNIT 1 '

DOCKET NUMBER.50-327 LICENSE NUMBER DPR-77

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, UNIT 2- '

DOCKET NUMBER'50-328 LICENSE NUMBER'DPR-79

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OPERATIONAL

SUMMARY

JULY 1990 UNIT 1 r Unit 1 generated 838,200 MWh (gross) electrical power during July, with a capacity factor of 95.23 percent. .

Unit 1 operated at approximately'100 percent reactor power level until 1816 Eastern daylight time (EDT) on' July 10, 1990, when the load war decreased '

f' 1. 140 MW, to 1,091 MW, to control condensate fluctuations. B-atring

.5 was isolated because extractiori steam had been isolated when a pipe oss2k occurred on B-2 heater drain to No.-3 heater drain tank!(HDT). Unit 1-reactor power level was reduced cc..approximately 98 percent. Unit 1 was- [

returned to 100 percent reac'.or nowerflevel. at 0530 EDT on July 12, 1990.-- i Further= problems wera experienced with the No. 3 HDT pump; and on. . i July 30,- 1990 . at 12T)9 ~ EDT, the :eactor power level was again decreat approximately 98 percent. Unit 1 remained at.98 percent power level L _.n the'end of July.

UNIT 2 Unit 2 generated 838,650 MWh (gross) electrical power during' July, with a capacity factor of 95.28 percent. Unit 2 operated at approximately 100 percent reactor power level until July 21, 1990, at 0736:EDT, when Unit 2 entered coastdown to-Unit 2 Cycle 4 refueling outage, uAt the end of July, Unit 2 was operating at approximately 91 percent' react r power level, f POWER-OPERATED RELIEF VALVES (?0RVs) AND SAFETY VALVES

SUMMARY

There were no challenges to PORVs or safety valves in the monthiof July. ,

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OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES There were no changes to the ODCM during the month of July.  !

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AVERACE DAILY UNIT. POWER LEVEL DOCKET NO. 50-327 UNIT,No.- One DATE: 02-90 ,

COMPLETED BY: T. J. Hollomon . TELEPHONE: (615)-843-7528 MONTH: JULY 1990-AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)' DAY (MWe-Net) 1 1016 17 1076 2 1107- '18 1107-3 1105 19 1107 4 1108 20 1075 5 1104 21' 1088 6 1105 22 1103- _;

7 1076 23. 1103- i i

8 1105 24 1104-  !

9 1103 25 -1105 '

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10 1093 26 1104 l' 11 1064 27 1105' t -  ;

l 12 1093 28 1103 i 13 1103 29 1103'

l. 14 1108 30 1091 15 1107 31  :-1074 ,

i 16 1088 1 L 1 f

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_, AVERAGE DAILY UNIT POWER LEVEL:

DOCKET NO. 50-328 UNIT No. Two DATE 1 08-02-90 COMPLETED BY: T. J. Ho11omon TELEPHONE:' (615) 843-7528' MONTH: JULY 1990 AVERAGE DAILY: POWER LEVEL AVERAGE DAILY POWER LEVEL-DAY- (MWe-Net) DAY ~(MWe-Net) 1 1111 17 1109 2 '1111 18 1108 ,

3 1110 _

19 1107' 4 1111 20 1106' -

5 1109 21 1097-6 1102 22 1085  ;

7 1104 23 1074-8 1105 24 1068 9 1105 25 1061 10 1106 26 1053 ,

11 1102 27' ~1045 12 1091 28- 1035' i 13 1100 29 1029' 14 1103 30 :1016 _

15 1111 31 1009 ,

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1107 1

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,,,: . . OPERATING DATA REPORT

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DOCKET NO. 50-327

. DATE Juount 3. 1990 COMPLETED BY T . 1. ' Holl omon TELEPHONE (615) 843-7528 OPERATING STATUS l Notes l-

1. Unit Name: , Sanuovah Unit One j- lL

2. Reporting Period:- .1ulv 1990 .l- l

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

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

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

7.- Maximum Dependable Capacity (Not MWe): _1148.0 l l 'j

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

N/A' f Power Level To Which RestricteJ. If Any (Net MWe): N/A

10. Reasons For Restrictions, If Any: N/A

. 1 This Month-- Yr-tr-Datei Cumulative ,

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11. Hours in Reporting Period 744 -5.087 79.632'

12. Number of Hours Reactor Was Critical 744.00 3.267.7 36.763

~ 13. Reactor Reserve Shutdown Hours 0 0 .- 0

14. Hours Generator On-Line 744.0 "3.167.1- 35.856.5

15. Unit Reserve Shutdown Hours 0.0 ' 0- 0 $

16. Gross Thermal Energy Generated (MWH)- 2.525.299.2- '10.205.044.5 116.540.924 ;I

17. Gross Electrical Energy Generated (MWH) 838.200 3.474.930 39.498.686 i

18. Het Electrical Energy Generated (MWH) 810.082 3.348.762- 37.820.791 }

19. Unit Service Factor 100.0 62.3 45.0 ';

20. Un(t Availability Factor 100.0 62.3 45.0- -l

21. Unit Capacity Factor (Using MDC Net) 94.8 57.3- 41.4

22. Unit Capacity Factor (Using DER Net) 94.8 57.3. 41.4 ,

23. Unit Forced Outage Rate , 0.0 -2.2 47.1

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

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

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l *1 l , ,, OPERATING DATA REPORT DOCKET NO. 50-328 DATE Auoutt 3. 1990-COMPLETED BY T. J . Hollomon TELEPHONE-.f615) 843-7528 OPERATING STATUS l Notes l, 1 Unit Name: Seouovah Unit Two l l

2. Reporting Period: July 1990 l_ l 3

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

4 Nameplate Rating (Gross HWe): 1220.6 l l --

5. Design Electrical Rating-(Net HWe); - 1148.0' -l l

6. Maximum Dependable Ca'pacity (Gross HWe): 1183.0 , l ;l-

7. Maximum Dependable Capacity (Net HWe): 1148.0 l 1

8. -If Changes occur in Capacity Ratings (Items Number 3 Throigh 7, Since Last Report. Give Reasons:

N/A .

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9. Power Level To Which Restricted,'If Any (Net MWe): N/A

10. Reasons for Restrictions, If Any: N/A fj This Month- 's-to-Cate Cumulative  !

11. Hours in Reporting Period 744 5.087 71:592 (

12. Number of Hours Reactor Was Critical 744,0 5.059.9 3a . 500 -  !

13. Reactor Reserve Shutdown Hours 0 0 -0'

14. Hours Generator On-Line 744.0 5.048.'4I 37.744.2

15. Unit Reserve Shutdown Hours 0.0 0' '

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16. Gross Thermal Energy Generated (MWH)- 2.487.332.6 16.'825.176.6' 117.235.437-

17. Gross Electrical Energy Generated (HWH) 838.650

18. Net Electrical Energy. Generated (MWH) 5.773.850 3 794.646 808.420 5.563.475 '38.011.809

19. Unit Service Factor '100.0~ 99.2 -52.7

20. Unit Availability Factor j

'. 0 0 . 0 99.2 '52;7 i

21. Ur!', Capacity Factor (Using HDC Net) 94.7 95.3 46.3-

22. Unit Capacity Factor (Using DER Net) ,j 94.7 95.3 46.3 :j

23. Unit Forced Outage Rate , 0.0 0.8 *

=41.5-l

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

Unit 2 Cvele 4' refuelina outaas is scheduled for Sootember 1990 with a duration of;70 ' dawn. l i

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25. If Shut Dom ^. i nd Of Report Period ' Estimated Date of- Startup: N/A j

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6 DOCKET NO:.._. 59 327 UNIT SHUlDOWNS AND POWER REDUCTIONS UNii NAid: Qag__ _,_,,,

DATE:__.DD/Dfd90. _ ,

REPORT MONIH: July 1990 _ COMPLETED BY:T. J. Ho].lgebn-TELEPPONE:(6151 843-7528 Method of Licensee Cause and Corrective . -

• Shutting Down Event Action to Duration Systgm Compgnent Type I Reason Reactor3 Report No. Code Code Prevent Recurrence 'l No. Date (Hours) l 6 900710 F A 5 At 1816 (EDT) on 7/10/90 B-string heater was isolated because of extraction steam isolation when a break occurred on B-2 heater drain to No. 3 HDT.

Power was reduced to

'l approximately 98 percent.

Unit I was at 100 percent reactor power level again on 7/12/90, at 0530 (EDI).

A 5 At 1259 (EDT) on 7/30/90, 7 900730- F reactor power level again was reduced to approximately 98 percent to reduce No.-3 HDT pump flow to increase delta P.

B-string heaters 2. 3. and 4 were isolated to repair leaks.

Unit-I was operating at 98 percent reactor power on 7/31/90 at 2400 (EDT).

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

I-Manual for Preparation of Data 5: Scheduled A-Eqripment failure (Explain)

B-Maihtenance 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 ( NOREG-061 )

E-Operator Training and License Examination 5-Reduction e F-Administrativa 9-Other G-Operational Error (Explain) SExhibit I-Same Source H-Other (Explair:)

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-s DOCKET NO: SL328

UNIT SHUIDOWNS AND POWER REDUCTIONS UNIT NAME: swo .['

DATE: 08/06/90 REPORT MONTH: July 1990 COMPLETED BY:T. J. Hollomon IELEPHONE:f6151 843-1528 , -

• Method of ticensee Cause and Corrective Duration Shutting Down Event Systp Cognent Action to No. Date Type 3 (Hours) Rtison 2 Reactor 3 Report No. Code Code Prevent Recurrence Unit 2 entered coastdown to Cycle 4 refueling outage at 0736 (EDT) on 7/21/93 and was operating at approminutely 91 perr.ent reactor power -level on 7/31/90.

Forced 2 Reason: 4

'3 Method: Exhibit G-Instructions 5: Scheduled 'A-Equipment Failure (Expeain) 1-N nual for Preparation of Data-

. B-Nintenance or Test 2-m nual Scram Entry sheets' for Licensee C-Ref uel ing : . Automatic Scram ' Event Report (LER)'Eile D-Regulatory Restruction

.. 4-Continuation'of. Existing Outage (NUREG-061)

-E-Operator Training and License Examination 5-Reduction

' F-Administrative .

9-ether G-Operational Error. (Explain)

-5 Exhibit I-Same Source H-Other (Explain) .

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