ML20096G669

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Monthly Operating Repts for Apr 1992 for Sequoyah Nuclear Plant Units 1 & 2
ML20096G669
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 04/30/1992
From: Hollomon T, Joshua Wilson
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9205260193
Download: ML20096G669 (10)
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l0 v y+ n ' ,.e b li a e t' w 1 May 15, 1992 U.S. Nuclear Regulatory Conunission ATTN 1 Document Control Desk Washington, D.C. 20555 Gentlement In the Matter of ) Docket Nos. 50-327 Tennessee Valley Author.ty d

) 50-328 SEQUOYAU NUCLEAR Pl>JiT (SQN) - AFRIL 1992 MONTilLY OPERATING REPORT Enclosed is the April 1992 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) 843-8924.

Sincerely, I

!MI .5 W

.. L. Wilson Enclosure cc: See page 2 9205260193 920430 s PDR ADOCK 05000327 [62/[ ,

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U.S. Nuclear Regulatory Commission Page 2 May 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 Conmission l One White Flint, North l 11555 Rockville Pike Rockville, Maryland 20852 .

Mr. Ted Marston, Director t Elect ric Power Research Institute P.O. Box 10412 Palo' Alto, Calit'ornia 94304 ,

i NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry-Road Soddy-Daisy. Tennessee 37379 i Regional Administration U.S. Nuclear Regulatory Commission i Office of Inspection and Enforcement Region II-101 Marietta Street, NW, Suite 2900 i 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

r. F. Yost, Directot 'Research Services Utility Data Institute 1700 K Street, NW, Suite-400 Wcshington, D.C. 20006 l

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TENNESSEE VAIJEY AUT110RITY NUClfAR PCMER CROUP SI'QUOYAll NUCLEAR PIANT l

l MONTill,Y OPERATING REPORT TO TIIE ,

NUCIEAR REGUIA11)RY COMMISSION

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APRAL_1992 l \

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' l UNIT 1 IX)CKET NUMBER 50-327 LICFNSE NUMBER DPR-77 I

i l UNIT 2 IX)CKET h0MBER 50-328 LICFASE NUMBER DPR-79 l

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OPERATIONAL

SUMMARY

APRIL 1992 UNIT _1 Unit 1 generated 243,180 megawatt hours (MWh) (gross) electrical power during April with a capacity factor of 29.11 percent. At the beginning of April, Unit I remained in a forced outage for resolution of ice condenser door problems and feedwater nozzle transition piece and elbow replacement.

On April 14 at 0758 Eastern daylight time (EDT), Unit 1 start-up was initiated. Criticality was reached oi, april 17 at 2309 EDT and tied on-line on April 18 at 0616 EDT. Unit I was taken to 100 percent reactor thermal power on April 23 at 1645 EDT.

On April 28 at 2023 EDT, Unit 1 experienced a reactor trip as a result of a turbine trip from a loss of load. The pressurizer power-operated relief valves (PORVs) opened, and Unit 1 entered Mode 3. The cause of the trip was determined to be a spurious operation of the sudden pressure relay on the transformer serving Phase B of the generator, resulting f rom a ground.

On April 29 at_-2226 EDT, while in the process of returning Unit 1 to service, Unit 1 experienced an automatic safety injection from low steam line pressure. All twelve steam dump valves had spuriously opened for approximately ten seconds. The main steam isolation valves closed and the emergency core cooling "ystem (ECCS) injected about 2500 gallons of borated water into the Unit i reactor coolant system.

Unit I remeined in a forced outage for steam dump valve control circuitry repair and replacement at the end of April.

1 UNIT _2 The Unit 2 Cycle 5 refueling outage continued throughout the month of April 1992. Core reload began on-April 11 at'0029 EDT and was completed on April 13 at 1754 EDT. Unit 2 entered Mode 5 on April 20 at 0117 EDT.

Unit 2 remained in Mode 5 at the end of April.

EDW err 0 FERATED_RELIE FJAW ES_AN D_S AEETLVAWESJ Um1A RY After the Unit 1 turbine and reactor trip on April 28, 1992, a pressurizer PORV lifted for a short duration (approximately 3-4 seconds), and tailpipe temperatures behaved as expected. Steam generator PORVs also lifted to compensate for the loss of load. There was no challenge to pressurieer l safeties.

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e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. __$0-127 UNIT No. __Dne DATE: 05-07-92 COMPLETED 11Y: L,1_llollomon TELEPl!ONE: 1615) 843-7523 1

MONTl!! Aralid212 i

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY DlWe-Brt) RAY (MWe-Net) 1 -5 17 -26 2 -5 18 __ 179 3 -5 19 359 4 -7 20 485

-5 21 1049 6 -5 22 1119 7 -7 23 1126 d

8 -5 24 _1133 9 -7 25 1134 j_ 10 -7 26 1132 11 -7 27 1132 12 -7 28 962 ___

I 13 -7 29 -12 I

f 14 -23 30 -12 15 -30 31 li/A 16 -23 i

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-_ ._. _ -_. _ ____ _ _ - _ . ... _.-_.. _ __ _ ___ _ ___.._- ..__._.____.__m_.. _

AVEBACE DAILY UNIT POWER LEVEL 1

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DOCKET NO. 50-328 UNIT No. Two DATE: _Q1.07-92 i COMPLETED BY: T. J. Ifollcracn TELEF110NE: 1615) 843-7523 MONTH: AERlL_,1912 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DM (MWe-Nel) DM (MWe-Ne.t) 1 -7 17 -9 2 .3 18 -9 3 -7 __._,_ 19 -5 4 -9 20 _ -7 5 -7 _ 21 -5 6 -9 22 -7 7 -9 23 -5 8 -9 24 -5 9 -9 25 -7 10 -9 _ 26 -5 11 -9 - 27 -5 12 -9 28 -9 I

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OPERA 11NG DATA REPORT DOCKET NO. 30:3P DA1E . May.Aj 99L__.

COMPLEILD BY 1, J.Jiollomon_.

TELEPHONE ILlh1.143_lLZB__

OPLPA11tG.11 AIV$ . . _ _ _ _ _ _ _

\ Notes l

1. Unit Name: ._$tqVoy8tLValL0nt _ ___ _ l l
2. Reporting Period: _ api 11_l292 l l
3. Licensed Thermal Power (HWt): _141LO _. l l
4. Nameplate Rating (Gross HWe): _1220 iL. ._ . _ . _ l l
5. Design Electrical Rating (Net HWe): _114 0 ,0__- . I i
6. Maximum Dependable Capacity (Gross HWe): _116 LD_ _._ _ l l
7. Maximum Dependable Capacity (Net HWe): _1112.0 _. } __}
8. If Chanks Occur in Capacity Ratings (Item Numbe s 3 Through 7) Since last Report, Give Reasons:
9. Power level '.o Which Restricted, if Any (Net HWe): . _MA
10. Reasons for Restrictions, if Any: __ NA_ _ ._.

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period _119 _ _Z ,201_ 91,.96S
12. Number of Hours Reactor Was Critical 2611L _ Zd3'd 42,089,L
13. Reactor Reserve Shutdown Hours . 0 0 0
14. Hours Generator On-Line 234,1 _ _ _ L12Sil 41,90h4__
15. Unit Reserve Shutdown Hours 0,0__ 0 D __
16. Gross Thermal Energy Generated (HWH) _ _1.19 210aZ._ __.6J 9.4.141 A.. _15b3064660_ .
17. Gros? Electrical Ens nv Generated (HWH) 243dB0 _,_1.30L 9 43.._._ _5L915d44
10. Net Electrical Ener,y Generated (t*"') 220,490__ __2.2 1 095_ __SQ ilBD . 02S_._. '
19. Unit Service factor 3513_ _ 231L _ 50d_ -

2C. Unit Availability Factor 3511 ILL .5015_.

21. Unit Caoacity Factor (Using HDC Net) 2B2 3 .___ 6610_ -

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22. Unit Capacity Factor (Using DER Net) _ 22.iL ____ . _6h15 4626__
23. Unit Forced Outage Rate 64.7 2LL 4 LQ._.
24. Shutdowns Scheduled Over Next 6 Honths t ijpe, Date, and Duration of Each):
25. If Shut Down At End Of Report Period. Estimated Date of Startup: _tiay_31_ '992 0

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

o e OPERATING DATA REPORT DOCKET NO. 50-328 DATE .jiar 7. 1992 -

l COMPLETED BY L l s.,lipilompa._  !

TELEPHONE IL15)_643-152E__ l i

OfEM11NLS1aIUS l Notes l

1. Unit Name: _$envonLunit in _ - - l l
2. Reporting Period: _Apr11J992 l l

- 3. Licens.J Thermal Power (HWt): 3411.0- l l 4 faameplate Rating (Gross HWe): _1220tL l l

5. Design Electrical Rating (Net HWe): _114010 l l
6. Maximum Dependable Capacity (Gross HWe): J.10110 l l 74 - Maximum Dependable Capacity (Net HWe): JJ2210 j l
8. If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since test Report. Give Reasons:  ;

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9. Power tevel to Which Restricted. If Any (Net HWe): N/A
10. Reasons For Restrictions, If Any: IMA.-

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period _ 719 2,90L 86,928 ,
12. Number of Hours Reactor Was Critical Q t0 _._ IdlL5 SDJ26
13. Reactor Reserve Shutdown Hours _ 0 0 0
14. Hours Generator on-Line 0.t0_ 1.70415 49JA7.7
15. Unit Reserve Shutdown Hours 0,.Q_ Q__ ,. A 16 r,ross Thermal Energy Genersted (HWH) 01 0_, Si l60413Zd 156J004035

--17. Gross Electrical Energy Generated (ffWH)- 0 ,_..Llh242fL _ __52,910.4557

18. Het Electrical Energy Generated (HWH) _h,16B 1405J43._ _ ._h0.630.907
19. Unit Service facto- .. Q 0_ 5&tl 5LZ_
20. Unit Availability factor. 0.0 58,Z_ $L2_
21. Unit Capacity f actor (Using HDC Net) 001 SLB._ 512 9 _
22. Unit Capacity Factor (Using DER Net) 0.0 SQif._ Sa,J _,
23. Unit- Forced Outage Rate 0J__ 2 if_ .__

35,3_

24. $hutdowns $cheduled Over Next 6 Honths (Type. Date, and Duration of Each):

,_. Unit _2_Cnl e_ Sat 19 elingaula ge _hegaa.Ma tdt.JLJ992..

25. If Shut Down At End 0f Report Period. Estimated Date of Stectun: Jujhj922 _

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DOCLCET Q: 50-328 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT f6ME: Two DATE: 05/07/9 L '

  • DE? ORT MONTH: Acril 1992 COMPLETED 9Y:T, J. Hqllomcn ".

TELEPSONE:(615) M3-752S ,

f Method of Licensee Cause and Corrective l Duration Shutting Down Event System Component Action to " l No. Date l Reason 2 Reactor3 5 Type * (Hours) Report No Code # Code Prevent Recurrence ' ,

2 ',20313 5 719.0 C 4 N/A N/A N/A Unit 2 entered Cycle 5 refueling outage at 2120 EST on 3/13/92 when the ur.it was reaeved from the "

gri d . Unit 2 Cycle S continues.

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I:F Forced 2 Reason: 3 Method: hhibitG-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparaticn 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 ( MJREG-kd)

E-Operator Training and License Examination 5-Reduction f

F-Administrative 9-Other i S

G-Operational Error (Explain) Exhibit I-Same Source  !

H-Other (Explain)

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