ML20127H086

Monthly Operating Repts for Dec 1992 for Sequoyah Nuclear Plant

ML20127H086
Person / Time
Site:	Sequoyah
Issue date:	12/31/1992
From:	Fenech R, Hollomon T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9301220185
Download: ML20127H086 (11)

Text

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Tennes%e Vadey Authcrity, Post Othce Dax 2000 Sodoy Desy. Tenressee 37379 2000 l

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Robert A Fenech v.ce President SeQAWi Nucles Plant i

January 15, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Centlemen:

In the Matter of

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Docket Nos. 50-327 Tennessee Valley Authority

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50-328 4

SEQUOYAH NUCLEAR FLANT (SQN) - DECEMBER 1992 MONTHLY OPERATING REPORT 4

Enclosed-is the December 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, wf Y

~Uk Robert-A. Fenech Enclosure cc:.See page 2 J

'9301220185 921231 i /

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U.S, Nuclear Regulatory Commission Page 2 January 15, 1993 cc (Enclosure):

INPO Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339-3064 Mr. D. E._LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Ted Marston, Director Electric Power Research Institute P.O. Box 10412 Palo Alto, California 94304 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy,-Tennessee 37379-3624 Regional Administration U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, NW, Suite-2900~

Atlanta, Georgia 30323-2711 Mr. B. A.' Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900-

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Atlanta, Georgia 30323-0199 Mr. F. Yost. Director Research Services Utility Data Institute 1700 K Street, NW,-Suite 400 Washington, D.C _20006-3800 m

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TENNESSKE VALLEY AUT110RITY NUClfAR POWER CROUP SEQUOYAll NUCLEAR PIANT MONTilLY OPERATING REPORT 4

TO *IllE NUCIEAR REGUIATORY C0t911SSION DECI'MBEIL1992 UNIT 1 IX)CKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 IX)CKET NUMBER 50-328 LICENSR NUMBER DPR-79 i

OPERATIONAL

SUMMARY

DECEMBER 1992 UNIT _1 Unit 1 generated 864.050 megawatthours (MWh) (gross) cicetrical power during December with a capacity factor of 99.95 percent.

At approximately 1146 Eastern standard time (EST) on December 15 the plant experienced a loss of control air pressure, resulting in turbine runbacks on both units.

Failure of the air compressor sequence selector switch prevented the compressors from loading, resulting in decreasing air pressure.

Timely operntor action was abic to arrest the control air pressure decrease and restore air presaure. Unit 1 was stabilized at 72 percent power.

On December 17 at 0200 EST, a power increase was initiated.

Unit 1 was operating at 100 percent renctor power level at 1002 EST on December 17.

On December 31 at 2148 EST, both units tripped as a result of a fault in the 500-kilovolt (kV) switchyard at the break 1r f or the intertie transf ormer.

Tenting was in progress on the breaker. When the fault occurred, the unit board voltage dropped and activated the reactor coolant pump undervoltage relays, which tripped the reactor. Unit 1 entered Mode 3 and remained in Mode 3 at the end of December.

UNIT 2 Unit 2 generated 846,185 MWh (gross) electrical power during December with a capacity factor of 97.88 percent.

On December 8 at 0944 EST, Unit 2 experienced a turbine runback and further manual reduction to 28 percent reactor power. A failure of the No. 3 heater drain tank (llDT) level controller relay initiated the transient. The No. 3 ilDT level control)er rela" was repinced and returned to service. Reactor power increase was initiated on December 8 at 1515 EST. Unit 2 was operating at 100 percent reactor power at 0427 EST on December 10.

At approximately 1146 EST on December 15 the plant experienced a loss of control air pressure, resulting in turbine runbacks on both units.

Failure of the air compressor sequence selector switch prevented the compressors from loading, resulting in decreasing air pressure. Timely operator action was able to arrest the control air pressure decrease and restore air pressure.

Unit 2 was stab)11 zed at 68 percent power.

On December 16 at 0200 EST, a power increase was initiated.

Unit 2 was operating at 100 percent reactor power level at 0905 EST on December 16.

On December 31 at 2148 EST, both units tripped as a result of a fault in the 500-kV switchyard at the breaker for the intertie transformer. Testing was in progress on the breaker. When the fault occurred, the unit board voltage dropped and activated the reactor coolant pump undervoltage relays, which tripped the reactor. Unit 2 entered Mode 3 and remained in Mode 3 at the end of December.

F0WER-01'ERATED_RELIELVALVESEORVs LAND _ S AFEILVALVES_

SUMMARY

There were no challenges to p0RVs or safety valves in December.

AVERACE DAILY UNIT P(WER IJNEL Doci:ET No. _50-327 UNIT No.._One DATE: 11/0$fR3 COMPLETED BY:

I._J _Ila110 mon TELEP110NE:.(.615)_843-1528 MONTil: DECESBER 129L AVE *, AGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY

--(Endict) -

DAY fWe-Net) 1 1152 17 1020 2

__.. _ _ 1153 18 1150 3

11.0 1 -

19 L15; 4

1017 20 1151.

5 1152 21 1151 6

115L 22 115L 7

1153 23 1151 8

.1112 24 1151 9

110A 25 1152 10 1141 26 1111 11 11AB_.

27 1111 12 11 M __

28 1110 t

13 1111 29 1151 l

14 1151 30 1154 15 L016 31 10A6 16 881 l

AVERAGE 11AILY UNIT POWER I.EVEl.

DOCKET NO.

__50-328 UNIT No. _Ivo DATE: _Q11_05/_23 COMPLETED BYt I._J aJlollomon TELEP110NE:

.(6151_8h3_12t28 MONTl!: DECEMDEIL19.92_

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY UNc NeD DAY DMe-lier) 1

.____ _.113 !t 17 1 136 2

J 13It 18 1136 3

lub_

19 1131 4

113tt 20 1137 5

._.__ ____113 L_.

21 L137 6

1135_._._ _ _

22 1137 7

_1135 23 1137 8

73 3 _

24 1133 9

B0h _.

25 1138 10 1127 26 lu8 11

_1133 27 1137 12 312It 28 1138 13

__113 3..

29 1137 14 113h.

30 1137 15 1002 31 1032 16 J0al

. 4 OPERATING DATA REPORT DOCKET h0. J0.JZZ DATE alLQh/33 COMPLETED BY L.JJallotnon_

TELEPHONE L611La&I52S_

OtLPA119L51AIUS jNotes l

1.

Unit Names _$equ0Jah_VnjL Qne l

l 2.

Reporting period: Dettmber_193Z l

l 3.

Licensed Thermal Power (HWt) 341LQ_

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4 Nameplate Rating (Gross HWe):._]2ZOJ l

l S.

Design Electrical Rating (Het HWe): 1140 0 l

l 6.

Hatimum Dependable Capacity (Gross HWe):,_1162.0 l

l 7.

Maximum Depondable Capacity (Het ifWe)!..lj22J l

-l 8.

If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasonst 9.

Power Level To Which Restricted, If Any (Net HWe):

N/A

10. Reasons ron Restrictions, If Any:

N/A This Month Yr-to-Date Cumulative

11. Hours in keporting Period ZA4 8.784

._10LBjl,_

12. Number of Hours Reactor Was Critical 741.8 7.79h0_

54J48

13. Reactor Reserve Shutdown Hours D _.

0 0

14. Hours Generator On-Line 74L8 LZED._

'535AL1

15. Unit Reserve Shutdown Hourn

. 0A Q_

0

16. Gross Thermal Energy Generated (HWH)_

Ld69.d6L4

_ZL365.311.4-174.977.844 17 Gross Electrical Energy Generated (HWH)

._3 ELD 50

_._BJZhdl8_ _

59J4L114-

18. Net Electrical Energy Generated (HWH)-

835.433 8.357.40S_

56.92LZZZ

19. Unit Service factor 99.7 Bad.

512_-

20. Unit Availability factor 91 7 00.1.,.

53.2..

21. Unit Capacity factor (Using HDC Net)

]QQJ 860

- 50.3

. 22. Unit Capacity f actor (Using DER Net) 97.8 82.9

' 49.2

23. Unit forced Outage Rate 0.3-11.9 38.5

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

Th CJ.Clf_LLtlutl1Dg RU1ASe is $thtdVltd._tpJtgin on April 2.1993. with a duration of 65 t

day h.,,

25. If Shut Down At End Of Report Period, Estimated Date.of Startup: _ Janupry 4. 1993 m:.:_ ;_.

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OPERATING DAT A REPORT 00CKti no. _ho 3Za DATE _D1100/31 COMPLETED DY L_AjiglicingL TELEPHONE (h15LB41-152b_

0fLPAllNG S.tAIV$

l l Notes 1.

Unit Name: _SequoyoLVnillwo l

l 2.

Reporting Period: _DestruhtrJ392 l

l 3.

Licensed Thermal Power (HWt): 141h0.

l l

4.

Nameplate Rating (Gross Hde): 1220,0 l

l S.

Design Electrical Rating (Net HWe):._1140A l

l 6.

Maximum Dependahle Capacity (Gross HWe): _116220 l

l 7.

Maximum Dependeble Capacity (Net HWe): _.1]Z Z4.0 l

l 8.

If Changes Occur in Capacity Ratings (Item Humbers 3 Through 7) Since Last Report Ulve Reasons:

9.

I'ower level to Which Restricted, If Any (Net HWe):

_._HIA

10. Reasons for Restrictions, if Any:

11/A_

This Month Yr-to-Date Cumulativt

11. Hours in Reporting Period JA4 B JBA___

9LSQ)

12. Number of Hours Reactor Was Critical 24148 7-ZD M -

._56 Zl?

13. Reactor Reserve Shutdown Hours 0

0 Il

14. Hours Generator On-Line ZA118 _

.L0lL 2_

$5E'. 4

15. Unit Reserve Shutdown Hours

_.020 0__

_ _. a

16. Gross Thermal Energy Generated (HWH)

_L46L B9111__.

__ZZ,25.4d6h1_

.12LIBL789

17. Gross Electrical Energy Generated (HWH) _D4hdB5 7.55 M Z0 _ __ 58.121 119

18. Net Electrical Energy Generated (HWH)

_ Bil.elh2

.__.l.17h11L _,

__561213.215

19. Unit Service Factor 99.7 8Q J

$ 913_ _

20. Unit Availability Factor 9917 8021_

_.$ 1_._

21. Unit Capacity Factor (Using HDC Net) 9L9 71,.S._

S0_ _

22. Unit Capacity Fector (Using DER Net) 95.7 72.1 52ta_

23. Unit Forced Outage Rate 0.3 Z12..

J kL_

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

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

Artua_ty_1L j293

i 6

DOCKE' NO:

50-227 LHIT NAME:

0-e UNIT Sh'JTDOWNS um POWER EDUCTIONS DATE:

01/0t/93 CCPPLETED Bf: k J J ellcmon GEFORT P*CNTH:_Pf2;fsR 1922 TELEPHONE:W 5) 6:3-75 2 Cause and Corrective l

Method cf Lic?nsee Duration Shutting Do m Event System Cocponent Acticn to l

No.

Date Type (Hourst Reason Reactor Report No.

Code #

Code Prevent Recurrence j

5 I

2 10 921215 F

A 5

50-327/92025 LF HS At approwimately 1146 EST. the plant e=perienced a loss of control air pressure. resulting in turbine runbacks on both units.

Failure of the air compressor seguence selector switch prevented the compressors f rom loading, resulting in decreasing air pressure. Unit I was stabilized at 72 percent power. The compressor sequence selector switch was replaced. On 12/17/92 at 0200 EST, a po-er increase was initiated.

11 921231 F

2.2 A

3 50-327/92027 FK BNR At 2143 EST, Unit I tripped as a result of a fault in the 500-kV switchyard at the breaker for the intertie transf ormer. Testing was in progress on the breaker. When the f ault occurred, the unit board voltage dropped and activated the reactor coclant pump undervoltage relays, which tripped the reactor.

Unit 1 entered Mode 3 and remained in Mode 3 at the end of December.

The breaker was subseq"entl y replaced and will be returned to service f ollowing testing.

Enhancements will be made for return to service methodologies i

for ir.itial commissioning of I

equipment.

3 Exhibit G-Instructions I

2 Method:

F: Forced Reason:

1-Manual for Preparation of Data 5: Scheduled A-Equipment Failure (Espiain) 2-Manual Scram Entry sheets for Licensee B-Maintenance or Test 3 Automatic Scram Esent Report (LER) File C-Refueling 4-Continuation of Existing Outage (NUREG-1022)

D-Regulatory Restruction E-Operator Training and License Examination 5-Reduction 9-Other F-Admi ni stra ti ve s-Eshibit I-Same Source G-Operational Error (Esplain)

H-Other (Explain)

+

-e i

DOCKET NO:

50 ~ 23 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME:

Twc DATE:

01/06/93 I

t REPORT MONTH: DEUMBER 1992 CONcLETED BY:T. A Ho11emon

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l TELEPHONE:(615) 843-7523 j

i l+

^

Method of l Licensee Cause and Corrective j

Duration Shutting Down l' bent System Co nponent Action to I

2 3

5 j

No.

Date Tpe (Hours)

Reason Reactor Report No.

Code Code prev *nt Recurrence 9

921208 F

A 5

50-328/92015 SD RLY At 0944 EST. Unit 2 experienced a j

turbine runback and further manual raduction to 28 percent reactor i.

power. A failure of the No. 3 j;

heater drain tank (HDT) level j

contrailer relay initiated the i

transient. The No. 3 HDY level i

j :-

controller relay was replaced and

[

j:

returned to service. Reactor power increase was initiated on i

i 12/8/92 at 1515 EST.

t i

10 921215 F

A 5

50-327/92025 LF H5 At approximately 1146 EST. the plant experienced a loss of control

{

j air pressure, resulting in turbine t

j runbacks on both units. Failure i

of the air compressor secuence l

selector switch prevented the i

compressors from loading, resulting in decreasing air pressure. Ur.i t 2 was stabilized at 68 percent power.

l The air compressor sequence selector switch was replaced and i

i i

returned to service. On 12/16/92 at 0200 EST a power increase us l

l initiated.

i i.

I 11 921231 F

2.2 A

3 50-327/92027 FK BKR At 2143 EST, Unit 2 tripped as a

[

result of a fault in the 500-kV i

switchyard at the breaker for the f

intertie transformer. Testing was j

l in progress on the breaker. When

.p l

the fault occurred, the unit board voltage dropped and activated the t

reactor coolant pug undervoltage l

relays, which tripped the reactor.

Unit 2 entered Mode 3 and remained in Mode 3 at the end of December.

l l

L b

I I: ForcedL 2

3 F

Reason:

Method:

Exhibit G-Instructions t

l:

5: Scheduled A-Equipment. Failure (Explain) 1-Manual for Preparation of Data t

l-B-Maintenance or Test 2-Manual Scras Entry sheets for Licensee l"

C-Refueling

.3-Automatic Scram Event Report (LER) File f

D-Regulatory Restruction

. 4-Continuation of Existing Outage (NUREG-1022)

{

i E-Operator Training and License Examination 5-Reduction i,

l F-Administrative 9-Other i

G-Operational Error (Explain).

Exhibit I-Same Source

[

.5 i..

H-Other (Explain) i

~)

DCCKET NO:

% 323 UNIT SHUTDOWNS AND POWER REDUCTIONS (MIT NAME:

Two CATE:

01/05/93 1

REPORT MONTH: DEEDAER 1992 C0ff2LETED BY:T.1 Molleecn TELEPHONE:(615) 843-75Z3 Method of Licensee Cause and Corrective a

Duration Shutting Down Event Systee Coseonent Action to l

2 5

No.

Date Type (Hours)'

Reason Reactor Report No.

Code #

Code Frevent Recurrence 1

11.

921231 F

~2. 2

.A 3

50-327/92027 FK SKR The breaker was subsequently 4

(cont.)

replaced and will be returned to servire following testing.

Enhancements will be made for return to service metitodologies for initial cossaissioning of equipoent.

l I

1 1

4 1

I: Forced Reason:

Method:

Exhibit G-Instructions 2

3 F

5: 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 S

G-Operational Error (Explain)

Exhibit I-Same Source H-Other (Expl sin),

.-=