ML20076M964

Monthly Operating Repts for Feb 1991 for Sequoyah Nuclear Plant Unit 1 & 2

ML20076M964
Person / Time
Site:	Sequoyah
Issue date:	02/28/1991
From:	Holloman T, Wallace E TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9103260239
Download: ML20076M964 (12)

Text

..

A

~~ ~~

$5swe vaney Auw tv post once tw rao scxm,.oa sy tennessee am9

~

March 15, 1991

{

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk '

Washington, D.C. 20555 Gentlemen:

In the Matter cf ) Docket Nos. 50-327 Tennessee Valtey Authority ) 50-328 SEQTYAH NUCLEAR PLANT (SQN) - FEBRUARY 1991 MONTHLY OPERATING REPORT s

Enclosed is the February 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.

Vary truly yours, TENNESSEE VALLE AUTHORITY E. G. Wallace, Manager Nuclear Licensing and Regulatory Affairs Enclosure cc: See page 2 9103260239 910228

-PDR ADOCK 05000327 PDR R i Teat

- _ _ !11

q r

'hy; ,:

, ^: - - ~' -

~~ '" - -' ~ ' ~- --

'.,. . Y

'w< WN[ t '

q <>

- .a -

& 10 _

c

>l3-  ;

-e < ,

[kf;  ;..

~

7h

-Q v- ' '

. :2I ,

2, . . .. , i i:,

e 'U.S.; Nuclear Regulatory Comission g  ! March 15,.1991 s -

-J cect(Enclosure):-

A: .Mr. J..N.--Donohev, Project Manager E U.S.2Nucleary Regulatory Comission'

.i

.One White--Flint,LNorth4-

~

4

-11555 J Rockville - Pike .-

Rockville, Maryland- 20852:

INPO' Records Center-

,, LInstitute of:NuclearlPowerfOperations j

1100 circle 70 Parkway, Suite 1500  ;

Atlanta-, Georg2a:.30389- l

< :Mr.;Ted Marston Director .

1 ElectricjPower,ResearchiInstitute J P.O.S Box 1104125 .

Palo Alto ; California: 194304- .;

He . .

..NRC Resident' Inspector;

' Sequoyah: Nuclear Plant -

2600<Igou Ferry Road:

=

Soddy-Daisy,.Tennesseej 37379

^'

'RegionaliAdministration-

, - U.S. - NuclearL: Regulatory Comission . , ,

_i9ffice ofrInspection and Enforcement--

LRegion II=

4

'101iMarietta Street.1NW, Suite 2900s  ;

, = Atlanta.: Georgia' 130323' a g ,

M i Mr. B.iA.7Wilsons Project Chief 1 a

U.S. L Nuclear l Regulatdry Comission '

negion?II?

]"

101fMarietta Street,;NW, Suite 2900 Atilanta p Georgia : ;30323 ;

t U _ EMr. Fred.Yost,:: Director, Research Services:

Utility;Dat'a;; Ins titute y~ 1700:K Street,-N.?W. <

~

Suite.400 ~

1 Washington TDC'20006' k

9 1

. f;!

' ' - - - -L  ; -- r

.D , -- ,.u. . ,, , ~ , , , -, , ,. - ,n,,,~

ps

~!

c TENNESSEE VALLET AUTHORITY NUCLEA1 POWER GROUP SEQUOYAR NUCLEAR PIANT .l

'l

-l MONTHLY OPERATING REPORT M ME NUCLEAR REGULATORY C0ffilSSION FEBRUARY 1991 1

1 UNIT 1 DOCKET NIMBER 50-327 l

. LICENSE NINBER DPR-77 ,

-i' UNIT 2

. DOCKET NIMBER 50-328  :

LICEMSE NDIBER-DPR-79:

'l 3 1

o

OPERATIONAL

SUMMARY

FEBRUARY 1991 UNLL1 Unit 1 generated 585,650 megawatt hours (MWh) (gross) electrical power during February, with a capacity factor of 75.0 percent. Unit 1 operated at approximately 100 percent reactor power level until February 18, 1991, at l 1601 Eastern standard time (EST), when a shutdown was initiated in accordance with technical specifications 3.1.2.4 and 3.5.2 for an inoperable centrifugal l charging pump (CCP). The actual pump failure, i.e., the inability of the CCP to develop adequate flow and discharge pressure, was the result of high recirculation flow caused by excessive wear of the wear rings and balance drum. A crack was also found in the pump shaf t. The cause of the crack and the excessive wear could not be determined, however the crack is considered to have been initiated months to years before the actual failure of the CCP

)

because of the oxidation present in the crack. Propogation of the crack was most probably a long term effect of high static and dynamic hydraulle loading l of the shaft. The unit was taken offline at 1927 EST, entered Mode 3 at 1955 EST, and entered Mode 4 at 0128 EST on February 19, 1991. On February 23, 1991, at 1454 EST, CCP 1B-B was declared operable following repair and testing. At 1502 EST on February 23, 1991, heatup to Mode 3 was initiated. Unit 1 entered Mode 3 at 1555 EST on February 23, 1991, entered Mode 2 at 0614 EST on February 24, 1991, and entered Mode 1 at 1346 EST on February 24, 1991. After resolving a problem with a voltage regulator, Unit I was tied online at 0110 EST on February 25, 1991. Unit i reached 100 percent reactor power at 0253 EST on February 26, 1991. At 0259 EST, Unit I received a balance of plant runback from 100 percent to 75 percent power as a result of opening of the level control valve 1-LCV-6-105B on the No. 3 heater drain tank (HDT) back to the condenser. At 0854 EST, further power level reduction was initiated to allow maintenance on the pressure differential indicator switch (PDIS) 1-PDIS-6-106A since investigation discovered that PDIS-6-106A initiated closure of 1-LCV-6-106B, resulting in a high tank level and the opening of 1-LCV-6-105B which initiated the runback. At 1015 EST, Unit i reached 65 percent reactor thermal power (RTP) to perform a calibration check on the PDIS. The PDIS setpoint was determined to be 15 to 20 pounds per square inch high. The PDIS was recalibrated and power level increase was initiated et 2017 EST. Unit i reached Ibv percent reactor power level on February 27, 1991, at 0120 EST.

On February 28,1991, at 1856 EST, numerous alanns were received on the main feedwater pump turbine (MFPT) along with turbine electro hydraulic control (EHC) and noisture separator reheater (MSR) panels. The problem was iden'.ified as n loss of the No. 1 preferred inverter. The electrical board was transferred to its alternate feeder, rnd plant conditions returned to normal. Losing the preferred inverter caused the MSR vsives to close, which resulted in a loss cf efficiency.

Unit I was operating at approximately 99 percent RTP at the end of February.

, OPERATIONAL SUP91ARY-FEBRUARY 1991 (CONTINUED) 1RIL2 Unit 2 generated 784.070 MWh (gross) electrical power during February, with a capacity factor of 100.4 percent. Unit 2 operated at apprnximately 100 percent reactor power level the entire month.

POWER-CPERATED RELIEF VALVES (PORVs) AND RAFETY VALVEILSINEERI There vere no challenges to PORVs or safety valves in February.

phi!'TL DOSE _ CAL (lH1ATION MAN 11A1. (QM31) M GES There were no changes to the ODCM during February.

' k AVERAGE DAILY UNIT POWER LEVEL

' DOCKET NO. . 50-327 UNIT No. One -- DATE: ;03-07-91 3 COMPLETED-BY 'T. J.'Hn110 mon

. TELEPHONE: -1615) 843-7528- .t

. MONTE: FEBRUARY 1991 -I

't AVERAGE DAILY POWER LEVEL AVERAGE DAll,Y POWER LEVEL

-IgI (MWe-Net) DM (MWe-Net' t

. . ~i ic 1132 17 1134 .

I 2.- =- 1135 18 866

'3: 1136- 19 -35

'4 1137- 20 -37 ._

.5, 1136 21 -35

'6 1135 22 -30 1

-7.

1135' 23 ,

~8. -1134 24 -28

,9 = 1135 25 373 '

? 10 . 1136 26 825-l 11L ~1136 27 1132 12L '1136 -28 1132=

4 ,

-13.4 -

1136' 29- -N/A ,

' 14 . '1136 30 N/A 15' 1134 31 N/A- r e 16' 1134 .

-l1337h' '- I

,, - s 4

r i

l

.. s

'v.  :-

,Q J;

.: -(

AVERACE ISILY UNIT POWER LEVEL

^

-DOCKET NO.' 50-328 UNIT No. Two DATEt _03-07 . -COMPLETED BY . I. - J. Ho11 ogen TELEPHONE: 1615) 843-7528; #

MONTHt EURUARY 1911 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWG-Jet) DAY (Miht-Eat )

1 1129 17 1131 2' 1126 18 1131 3 1129 19 1130

'4- 1129 20 1130

'5 1131 21 1129 3 h.'

6 '1132 22 1129 7- '1131 23 1131 .

8i ._. 1132 24 1130 .

9- 1132 25 1131

- 10- '1132 _ 26 1133 11: 1133 27 1132 1132- 28- 1132

.13 1130' 29 N/A 14 '1131' 30 __ N/A 15 1132 31 N/A

-16 1132'  ;

l:'

I

U OPERATING DATA REPORT DOCKET NO. J0-327 . .

DATE Har. 7. 1991 COMPLETED BY W ollong L TELEPHONE 161hLSf3-162B_

Of1RAIING 11AIU1 l Notes l

1. Unit Name: _Stau2Jah Unit One l l

2. Reporting Period: J.abruary 1991 l l

3. Licensed Thennal Power (HWt): 341LD l l

4. Nameplate Rating (Gross HWe): _12ZD.i6 l l

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

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

7. Maximum Dependable Capacity (Not HWe): 112LQ  ! .J

6. If Chariges Occur in Capacity Ratings (Items Number 3 Through 7) $1nce Last Report, Give Reasons:

9 ._ Puwer Level in Which Restricted, if Any (Not HWe): N/A

10. Steasons for Restrictions, If Any: N/A This Month Yr-to-Date Cumu'lative

11. Hours in Reporting Period 672 .1. 4 l6_ 84,121

12. Number of Hours Reactor Was Critical . 541J9_ , _.1.285.3 41.357

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-line 522.3 .L266J._ 40.362.3

15. Unit Reserve Shutdown Hours 0.0 0 0

16. Gross Thermal Energy Generated (HWH) 1.717.351.7 4.253.841.1 131.539.908

17. Gross Electrical Energy Generated (HWH) . 585.650 1.457.130 44.577.716

18. Net Electrical Energy Generated (HWH) ._562.375 ._. 1.403.056 42.699.932

19. Unit Service Factor 77J _ 89 d 47.6

20. Unit Availability Factor 77.7 89.4 47.6

'21. Unit Capacity Factor (Using HDC Net) 74J 88.3 441 9 _

22. Unit Capacity Factor (Using DER Net) 72.9 _ 86 3., 43.9

23. Unit Forced Outage Rate 22.3 10 1 44.6

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: N/A

OPERATING DATA REPORT DOCKET NO. _50-328 DATE _Nar. 7. 1991 COMPLETED BY I. 1. Hollomon_

TELEPHONE 16151 843-1528 _

QfERATING STATUS l Notes l

1. Unit Name: _,_itAuoyah Unit.Two l l

2. Reporting Period: .,_Idryary 1991 l l

3. Lic6nsed Thermal Power (HWt): ,,,3411.0 l l

4. Nameplate Rating (Gross HWe): 1220d,,,_ . _ , , _ l l

5. Design Electrical Rating (Net HWe): 1148.0 l l 6.. Maximum Dependable Capacity (Gross HWe): ,,1152J l l

7. Maximum Dependable Capacity (Net HWe): .1122.0 j. I

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

9. Power Level To Which-Restricted. If Any (Net HWe): N/A

10. Reasons For Restrictions,' If Any: N/A This Honth Yr-to-Date Cumulative

11. Hours in Reporting Period 672 1,416 76.681

12. Number of Hours Reactor Was Critical 672.0 1.416.0 41 887

13. Reactor Reserve Shutdown Hours 0 0 _ 0

14. Hours Generator en-Line 672 0.. 1.379.0 4Q,939.4 .

15. Unit Reserve Shutdown Hours 0.0 0 0

16. Gross' Thermal Enugy Generated (HWH) _1,287.530.1 4.604.190.4 ,_126_.878.641

17. Gross Electrical Energy Genereted (HWH) 784.070 1.575.220 _,43JnM16

18. Net Electrical Energy Generated (HWH) 756.687 1.518.]l62 41.144.M0

19. Un't SJrvice Factor 10$.0 97.4 53.4

20. U.It Availability Factor 100.0 97.4 53.4

21. U.dt Capacity Factor (Using HDC Net) 100.4 95d_ 47.8

22. Unit Capacity Factor (Using DER Net) 48.1 . 93.4 46.7

23. Unit Forced Outage Rate 0.0 2.6_ 39d__

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: .N/A i

.E DOCKET NO: 50-327 UNIT SHUTDOWNS AND POWER REDUCTf0NS UNIT NAME: Qne DATE: 03/07/91 -

REPORT MONTH: February 1991 COMPLETED BY:T.1. Pa11omon TELEPHONE:(6151 843-7523 Method of Licensee l Cause and Corrective Duration Shutting Down Event Systy Compgnent Action to No. Date Type l (Hours) Reason 2 Reactor 3 Report No. Code Code Prevent Recurrence i 1 910218 F 149.7 A 1 50-327/ BQ P Unit I was taken offline at 1927 91003 EST on 2/18/91 in accordance with TSs 3.1.2.4 and 3.5.2 for inoperable CCP. On 2/23/91 at 1454 EST, CCP 18-8 was declared operable af ter maintenance and testi.ig. The actual pump failure was the result of h:gh recirco-lation flow caused by excessive wear of the war rings and balance drum. A crack was also found in the pump shaft. The cause of crack and excessive wear cov1d not be determined. The crack is considered to have been initiated months to years before the actual failure of the CCP.

Prorogation of the crack was most probably a long term effect of high static and dynamic hydraulic loading on the shaft. The pump was repaired and returned to service. - At 1502 EST on 2/23/91 permission was given to begin heatup to Mode 3. Unit I was critical at 0614 EST on 2/24/91, and reached 100 percent reactor power level at 0253 EST on 2/26/91.

I:F Forced 2 Reason: 3 Method: 4xhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Mar:ual for Preparation of Data B-Naintenance 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-Admini strati ve 9-Other G-Operational Errer (bolain) SExhibit I-Same Source H-Other (Explain)

n.

~

. DOCKET N0: 58-328 *-

UNTT SHUTDOWS AND POWER REDUCTIONS . (MIT MAME: one

~

DATE: c3/07/91 2 -

_ REPORT MONTH: . February 1991, ' COMPLETED BY:T. J. Holl--

TELEPHONE:(6151 843-7528 Method of; Licensee -Cause and Corrective Duration Shutting Down Event -- Systy Action to:  ;;

.No. Date' Type l_ (Hours): Reason 2- Reactor 3 Report No. ' Code C9 Code. ent Prevett Recurrence.

21 910226 F A: 5 - IT- LC On 2/26/91 at 0259 EST, the' ~

unit received a balance of plant runback fross 100 percent to 75 percent reactor power because '

1-LCV-6-1058 on the No. 3 HDT .

opened. Further power reduction was initiated at 0854 EST to

a. low maintenance on 1-PDIS-6-106A 4

since investigation discovered that PDIS-6-196A initiated closure

.h' of 1-LCV-6-1068 closed resulting in a high tank level and opening -.

1-LCV-6-1058 which initiated the -

runback. The PDIS setpoint =es

- found to be 15 to 20 psig higher -

than normal. It was recalibrated and power level increase =ms .

initiated at 2017 EST.- Unit I was again at 100 percent reactor level on 2/27/91 at G120 EST.

4 4

I:F Forced 2 g,, son: .

3 Method: h ibit G-Instructions 5: Scheduled A-Equipment Failure (Explain)~ 1-Manual .for Preparation of Data B-Naintenance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling. 3-Automatic Scram Event Report (LER) File

- D-Regulatory Restruction 4-Continuation of Existieg Outage OeJREG-1922)

. E-Operator Training and License Examination .5-Reduction"  ;

F-Administrative! . ..

9-Other '

G-Operational- Error (Explain) - 5 Exhibit I-Same Source- i H-Other (Explain) [

i 1

3 .6 _. - -

1. g c-. s.

• C4 . .

_ DOCKET NO: "50-328' -'

~~ '

- UNIT, SHUTDOWNS AND POWER REDUCTIONS UNIT NAME: Tum .

DATE: - 03/07/97 a --

REPORT MONTH: Februarv 1901- ' COMPLETED BY:T. J. tiellemma TELEPHONE:16151 843-7528 i Method of . Licensee .

. Canse and Corrective Duration Shutting Downi Event Systy. Action to-No. .Date Type l (Hours): Reason 2. Reactork Report No.. Code -

C Co yde t

Prevent Recurrence" '

No activities during February.

1991.

i 4

k t

l I:F Forced 2 Reason: . -hthod: Dibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) .1-8tanual - . 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-10Z2) .

E-Operator Training and License Examination 5-Reductien F-Administrative 9-Other G-Operational Error (Explain).. 5 Exhibit I-Same Source H-Other (Explain)-

s q , ,,E+ ww, . ~-g- y :c- s.w-. y. -. ,y mg.  %.3 +.--wg

- e. ,3