Text

Monthly Operating Rept for Jan 1984
	ML20080T893
Person / Time
Site:	Beaver Valley
Issue date:	01/31/1984
From:	Carey J, Holtz J; DUQUESNE LIGHT CO.
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8403020086
	Download: ML20080T893 (12)
	v • d • e

. .

OFERATI G DATA REPORT DOCKET NO. 50-334 DATE 2_7.pa COMPLETED BY J. L. Holtz

.' TELEPHONE. 417 441 1369 OPERATING STATUS .

I. Unit Name: Beaver Valley Power Station. Unit #1 Notes

2. Reporting Period: January 1984

3. Licensed Thermal Power (MWt): 7AA0

4. Nameplate Rating (Gross MWe): 923 5.' Design Electrical Rating (Net MWe): 835

6. Maximum Dependable Ct;paci:y (Gross MWe): 860

7. Maximum Dependable Capacity (Net MWe): 810

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

9. Power Level To Which Restricted.If Any (Net MWe): None

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

!!. Hours in Reporting Period 744 744 67.968

12. Number Of Hours Reactor Was Critical 718.0 718.0 31,597.4

13. Reactor Reserve Shutdown Hours 0 0 4,482.8

14. Hours Generator On-Line 656.1 656.1 30.434.9

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1,552,319 1.552.319 69.141.857.3

17. Gross Electrical Energy Generated (MWH) 503,800 503.800 21.932.740

18. Net Electrical Energy Generated (MWH) -

478.477 478.477 20.367.365

19. Unit Service Factor 88.2 88.2 46.9

20. Unit' Availability Factor .

88.2 88.2 46.9

21. Unit Capacity Factor (Using MDC Net) 79.4 79.4 40.4

22. Unit Capacity Factor (Using DER Net) 77.0 77.0 39.2

23. Unit Forced Outage Rate 11.8 11.8 30.7

24. Shutdowns Scheduled Over Next 6 Months (Type. Date and Duration of Eselil:

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

26. Units in Test Status IPrior to Commercial Operation): Forecast Achieved INIT!A L CRITICA LITY N/A _ N/A N/A INITIAL ELECTRICITY N/A COMMERCIA L OPERATION N/A N/A e403020086 840131 PDRADOCK05000g ggj77)

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I AVERAGE DAll UNIT POWER LEVEL DOCKET NO. 50-334 UNIT 3US U:'1: # 2-DATE 2-7-84 COMPLETED BY J. L. Hol tz TELEPHONE (412) 643-1369 Janaury 1984 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mwe. Net) (Mwe.Nes t 817 17 821

, 825 817

. 18 3 _

825 39 - 774 4 A?1 :o nin 830 21 A?1 5

6 809 3 829 7 ?'S 23 895 584 24 821 3

9 791 25 7C4 Io 799 26 252 7AO 248 11 27 l

12 0 23 482 l

525 676 13 29 14 613 30 759

'An 31 821 15 16 825 INSTRUCTIONS On this formst. list the averup daily unit power lesel in MWe-Net for each day in the reporting munch. Compute to the nearest whole rnepwast.

l (9/77)

- rw UNIT SHU1 DOWNS AND POWER REDUCTIONS DOCKET No.30-334 UNITNAME BVIS Unit il DATE 2- 7-R4 REPORTMONilg' Januar_y COMPLETED IlY L Holtz TELErtlONE 12) 643-1369 T -

N '. Ib'e 5 3j }4 ){f Licensee !g f"t Cause A Cinactaise eg .a ; ec Eveni ui 9 Asti,,n si.

$E #E j5g Repost 8 N0 j'3 Prevent Recuirente 6

1 1/11/84 F 36.0 F 5 N/A HC HTEXCH The station was in Operational Mode 1 at 100 percent reactor power, but had been experiencing high cation conduc-tivities in all three steam generators.

The station was taken off-line at 0903 hours0.0105 days 0.251 hours 0.00149 weeks 3.435915e-4 months in order to begin draining and fil 'rq of the steam generators to improw secondary plant chemistry.

This was completed at 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months on the 12th. The Main Unit Generator was i synchronized to the grid at 2144 hours0.0248 days 0.596 hours 0.00354 weeks 8.15792e-4 months on the 12th.

I 2 3 4 l~: Fused Reason:

S: S(hedu!cil Hethod: Exhibit G - Insisus tions A.Equiprnent FailuretExplain) 1-Hanusi fin Picparation of Dan Il-Maintenance ei Test 2-Hanual scram C Refueling 1:ntr> Sheets for Licensec 3-Automatic Scram liven Rcrine 81.1 Ri f alc t MIRI G D-Regulatus) Restsiction 4-Continued From Previous Month Olbil l'-Opesalin Training A 1.itcuse !!xarninati""

5-Reduction is Administ rative 9 0th?r 5 i G Operatiinsal l'oine (l~ xplain) 13hibit I - Sanw,S uns e i l'8/77) II Othe: IEsplain t

m IINITSHUTDOWNS AND POWER REDUC 110NS DOCKET NO. 50-334 UNIT NAME BVPS l' nit #1 DATE 2-7-84 J. L. Hol tr _ _

REPORT MONIll January COMPLETED HY .

TELErtlONE f 41M 643-1369

s. Da e-7

.5'E 3 :: 4 2 5

[g'=j l.icensee tveni

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k p raine A r... esine A ti,,,, n,

$5 2 j ;?3 g Report :r WO j0 Prevent itecurrente d

2 01/14/84 F '15.2 H '3 84-1 HA TURBIN The station experienced a turbine /

reactor trip at 1957 hours0.0227 days 0.544 hours 0.00324 weeks 7.446385e-4 months on the 14tt while operators were performing a r :gularly scheduled check of the low bearing oil trip device on the main turbine. The exact cause of the trip has yet to be detennined, although it appears that the combination of re-duced oil pressure, induced during th e check, in conjunction with the inher-ent turbine vibrations were sufficieni to actuate one of the auto stop oil pressure switches. These were checke<

for calibration and all were found to be within their calibration limits.

I 2 3 4 F: F.uted Reason: efethod: 1:sinbit G. Instenttions 5' Schedn'cil A.Lyuipenent Failuse(Explain) 1-tranual for Pseparation of Data i B-Maintenance ci Test 2-Manual Scram I ntry Sheets f or 1.icensee r Refurling 3-Automatic Scram ISent Repost il l'Ri l eIc t NllRI G D.RcFulatnr> Resitiction 4.Continned From Previous Mont.h 0161) l' Openaln Tiaining A License I:xaminatiim 5-Rei*uction l~ Administrative 9-Other 5 G Operational l's sur 11:xplaini

(**J77) ITinhit I S.nne S. mise 11 Other IEsplain)

=m UNITSHUTDOWNS ANI) POWER REDUCTIONS IX)CKET NO. 50-334 UNIT NAME BVPS Unit #1 DATE 2-7-84 REPORT MONIII ' January COMPLETED BY J. L- I!altz IEl.ErtlONE (412) 643-136_9 s

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-, .E E s ~ .5 X l.icensee [-t, h, ('ause & ('oe res tise i

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$5 E Repoel AU E' Prevent Resurrente 3

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3 01/25/84 F 14.9 G 3 84-2 IB INSTRU- At 0305 hours0.00353 days 0.0847 hours 5.042989e-4 weeks 1.160525e-4 months , a reactor trip / safety injection occurred during performance of the bimonthly maintenance surveil-lance procedure on the Reactor Protection Logic System, Train "A".

The trip occurred when the reactor operator depressed the " SIS Train B Reset / Override" pushbutton as instruc-ted by the procedure. Feedwater isolation occurred and the Auxiliary Feedwater Pumps began supplying the Steam Generators. The plant was quickly stabilized using the appro-priate emergency cperating procedures.

The safety injection, CIA, and Auto Changeover signals were reset at 0320 hours0.0037 days 0.0889 hours 5.291005e-4 weeks 1.2176e-4 months and normal charging and letdown were restored. (Continued)

I : 3 -t f: f uted Reason: trethod:

S 5(heilu'ed A lquipment failure (Explain) Exlisbit G - Insitut tions 1-Manual lo' P8cpasanon of Dasa R Maintenance of Test 2-M.inunt scram C Refueling 1.nts) Sheets 80' l.icenwe 3-Automatic Scram- lient Regwnt 8l l RII sic (NilRE G D Regulatin) Restriction

4-Continued From Previous tionth DIt Il l' Opcialns Training A litenw I:xaininstion 5-Reduetton I Adeninistr.iiire 9-Other "

G Operational l esos ll:xpl.iin t .

l'7/77) It Othes ilhpl.ain t I stubit I Sanic Sunse

,--- m UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-334 UNIT NAME BVPS Unit #1 DATE 2-7-84 January COMPLETED BY J. L. Holtz REPORT MONTH TELEPHONE (412) 643-1369 C ee 3

T =Jes f C y"- y 55 E ijy liccH5cc P. % Cause A Correttise g#

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_E 5 ac Event Repor: =r s2 AG h V A ,i, o j5j Prevent Recurrente d

3 01/25/84 F 14.9 G 3 84-2 IB INSTRU At 0322 hours0.00373 days 0.0894 hours 5.324074e-4 weeks 1.22521e-4 months , the 1B Low Head Safety Injection Pump was secured and the lA Main Feedwater Pump was restarted at 0324 hours0.00375 days 0.09 hours 5.357143e-4 weeks 1.23282e-4 months . All three auxiliary Feedwater Pumps were shut down at 0328 hours0.0038 days 0.0911 hours 5.42328e-4 weeks 1.24804e-4 months . The maintenance surveil-lance procedure is being reviewed at this time.

I I 2 3 4 f: Faiced Reason: Method:

S: Schedti'ed Exhibit G - Instrut tions A. Equipment Failure (Explain) 1-Manual fin Pieparasi.m of Data B-Maintenance of Test 2-Manual scram C. Refueling Entr> Sheets lor t iccusee 3-Automatic Scram Event Repius fl.I RII de tNURI G D-Regulator) Restriction 4-Continued From Previous Month Olbil E-Opesatos Training & l.icense Examination 5-Reduction E Administrative 9-Other 5 G Opeutiental 1 nos ll:xplain t IThibit 1 Same,Souisc 19/77) II Other (E splain )

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'UNITSHUTDOWNS AND POWER REDUCTIONS DOCKEINO. 50-334 UIVIT NAME - _BVPS U"It #1 DATE 2-7-84 REPORT MON 111 January COMPLETED BY 1 I. Mnity TELErilONE (412) 643-1319 sa. Da,e -)

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.e E 34 2h55') ac 1 ice"5cc Event E*.

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9. 3 came A roeiestisc At t ' .,n t o 33 $ j di j Repine = NC y' Prevens Recurrente l

4 01/26/84 F 21.8- F 5 N/A HC HTEXCH At 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months on the 26th, a reduc-tion in reactor power was begun in

, order to locate an apparent condenser

! tube leak. The.1C Condenser Waterbo) was isolated at 0804 hours0.00931 days 0.223 hours 0.00133 weeks 3.05922e-4 months . With conductivity problems in all three steam generators, it was decided to enter Mode 2 at 0826 hours0.00956 days 0.229 hours 0.00137 weeks 3.14293e-4 months . The mair i

unit generator was taken off-line at 0917 hours0.0106 days 0.255 hours 0.00152 weeks 3.489185e-4 months . Operations began feeding and bleeding the condenser hotwell ir an attempt to improve secondary plant

chemistry. Chemistry had improved

sufficiently by 0450 hours0.00521 days 0.125 hours 7.440476e-4 weeks 1.71225e-4 months to allow

' the station to go on-line. The main unit generator was synchronized to tte grid _at 0707 hours0.00818 days 0.196 hours 0.00117 weeks 2.690135e-4 months .

I 2 3 4 f: f uted Reason: tiethod:

S: Schedu!cil A. Equipment Failure (Lxplain)

Extubit G Instinttiims 1-rtanua l lin Pseparati ni of Data B4taintenance ei Test 2-Manual Scram C Refueling 1:sitr> Sheets tan I kemec 3-Automaeic Scram ISen ReinnI il i It i i de t NIIRI G D Regulatus) Resitiction

', I -Ope ator Tsaining & I.icense I:xainination 4-Continued From Previous Month O t til l i 5-Res'oc tion 1%Adnsnistrative 9-Other 5 G Operational I e ros 11 xplain t ,

t't/77) !! Othes (lisplaini IT1uhit I - Same Souisc i

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Telephone (412) 3934000 P. . B x 4 Shippingport, PA 15077 @ 04 February 9,1984 Beaver Valley Power Etation, Unit No. 1 Docket No. 50-334, License No. DPR-66 Monthly Operating Report United States Nuclear Regulatory Commission Director Office of Management Information and Program Control Washington, D.C. 20555 Gentlemen:

In accordance with Appendix A, Technical Specifications, the Monthly Operating Report is submitted for the month of January 1984.

Very truly yours, J J. Carey Vice President Nuclear Division Enclosures cc: NRC Regional Office, King of Prussia, PA

$b

NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE - JANUARY 1984

' January 1 - The station was in Operational Mode 1. with reactor power through _ .at a nominal 100 percent. The. Reactor. Coolant System was

- January 5 at _ normal' operating temperature and pressure.

January 6 The station was in Operational Mode 1. A load reduction through. to 70 percent reactor power was begun at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months in January 7 order to remove the 1A Condenser Waterbox from service

- for tube cleaning. The 18 and IC Main Feedwater Flow

. Regulating Valves wera placed on clearance for repair of their actuators.

~ While stepping the rods in, a rod control urgent alarm was received. Reactor power was held at 90 percent while the problem was being investigated. The cause was found to be several bad failure detection cards in tha rod con-x trol power cabinets. At 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months on the seventh, reacter power reduction to 30 percent was begun using boration.

The IB 'and IC Main Feedwater Regulation Valves were returned to service at 0215 hours0.00249 days 0.0597 hours 3.554894e-4 weeks 8.18075e-5 months .. Reactor power was increased to 45 percent.

LJanuary 8 .At 0135 hours0.00156 days 0.0375 hours 2.232143e-4 weeks 5.13675e-5 months , a reactor power increase was begun, with holds at every 5 percent power intervals to allow monitoring of. Main Feedwater Regulator Valves. Reactor power was held

at.70 percent at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months due to condenser tube cleaning that was in progress. A power increase was begun at 2358 hours0.0273 days 0.655 hours 0.0039 weeks 8.97219e-4 months .

l January 9 Reactor power was ' increased to a nominal 100 percent with~

-through the 1A Condenser Waterbox out of service for leak checking January 10_- and tube plugging. The Reactor Coolant System was at normal

, operating temperature and pressure.

' January 11- .The station was in Operational Mode 1 with reacter power at a-nominal 100 percent. At 0903 hours0.0105 days 0.251 hours 0.00149 weeks 3.435915e-4 months , it was decided to

enter Mode 2 due to high cation conductivity in all three steam generators. The station was taken off-line and Operations.begain draining and filling the steam generators in an attempt to improve the feedwater chemistry. Reactor power was being maintained at 2 percent.-

January 12 [ Leak _checkingoftheMainCondenserwas.inprogress. At

, L2030. hours, all steam generator feedwater conductivities were within chemistry specifications. The Turbine was y rolled, 'and a power. escalation was begun. The Main Unit Generator was synchronized to the grid at 2144 hours0.0248 days 0.596 hours 0.00354 weeks 8.15792e-4 months .

7 Reactor power was' increased to 20 percent.

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- January 13 Reactor power was increased to 50 percent at 0148 hours0.00171 days 0.0411 hours 2.44709e-4 weeks 5.6314e-5 months .

A second escalation was begun at 0345 hours0.00399 days 0.0958 hours 5.704365e-4 weeks 1.312725e-4 months . Reactor power was held at 65 percent at 0620 hours0.00718 days 0.172 hours 0.00103 weeks 2.3591e-4 months while repairs

~;. were being made to the Circulating Water Outlet Valve on '

the 1B Waterbox of the Condenser. At 0955 hours0.0111 days 0.265 hours 0.00158 weeks 3.633775e-4 months , a load

-increase was begun to a limit of either 90 percent reactor power or 30*FJFI on any. condenser waterbox. The IB Water-box remained isolated for leak checks.

The IB Condanser Waterbox was placed in service at 1245 hours0.0144 days 0.346 hours 0.00206 weeks 4.737225e-4 months . The ID Waterbox was placed on clearance and drained

for tube leak _ checking.

January 14 The leak' check'ing and' plugging of d6Tective condenser tubes

. was . completed at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months . The 10 Condenser Waterbox was

_placed in_ service at 0510 hours0.0059 days 0.142 hours 8.43254e-4 weeks 1.94055e-4 months . An increase to 100 percent !

reactor power began at 0520 hours0.00602 days 0.144 hours 8.597884e-4 weeks 1.9786e-4 months . A nominal 100 percent i reactor power was: reached at 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months .

4 ' At 1957 hours0.0227 days 0.544 hours 0.00324 weeks 7.446385e-4 months , a reactor / turbine trip occurred during performance of a bearing oil- pedestal check on the turbine.

The plant was stabilized in Mode 3.

January 15 The reactor was taken critical at 0843 hours0.00976 days 0.234 hours 0.00139 weeks 3.207615e-4 months . The Main Unit Generator was synchronized to the grid at 1106 hours0.0128 days 0.307 hours 0.00183 weeks 4.20833e-4 months .

Reactor power escalation was begun and reached at 100.

E- percent at~1500-hours.

January 16 -The station was in Operational Mode 1 with reactor. power

, through- . .at'a.monimal 100 percent. The Reactor Coolant System was January.18' at normal operating temperature and pressure. At 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months , a decrease in . reactor power was begun in preparation for isolation of the IC Condenser Waterbox.

, January 19 LAt,0000 hours0 days 0 hours 0 weeks 0 months , reactor power'1evel was held at 80 percent i- and the IC Condenser Waterbox was isolated. The isolation

was completed at 0120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months and draining was begun. Reactor power was _ increased' to 90 percent for performance of a L ' calorimetric.- At 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months , the cooling tower pump suction pressures and the. condenser hotwell temperatures were such

-that reactor power could be increased to a nominal 100 percent.

r~ -

This-was. achieved.at 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months , s January 20 A nominal = 100 percent . reactor power was being maintained

' - with' the 1C ~ Condenser _Waterbox isolated for tube leak fchecking and-plugging. -This was completed by 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months and the IC Waterbox was placed in service at 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months .

January 21 The station was 'in Operational Mode 1 with reactor power through' . at a nominal 100 percent. The reactor coolant system was January 24 - ~ Tat normal-operating: temperature and pressure.

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January 25 During performance of a Maintenance Surveillance Procedure on the solid' state protection System, Train A, a Train B safety injection was inadvertently actuated at 0312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months .

The safety injection was terminated and reset after success-ful completion of emergency operations and termination !

criteria. The plant was stabilized in Mode 3. !

At 0615 hours0.00712 days 0.171 hours 0.00102 weeks 2.340075e-4 months , the 1A Condenser Waterbox was isolated and draining begun for tube leak checking and plugging. After completion of start-up requirements, the reactor was taken l critical at 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months . The main unit generator was synch- i ronized to the grid at 1812 hours0.021 days 0.503 hours 0.003 weeks 6.89466e-4 months . Reactor power escalation I was begun.

January 26 The station was in Operational Mode 1 with reactor power at 93 percent. At 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months , a reduction in power was begun in order to locate an apparant condenser tube leak. The IC Condenser Waterbox was isolated at 0804 hours0.00931 days 0.223 hours 0.00133 weeks 3.05922e-4 months . With conductivity problems in all three steam generators, it was decided to enter Mode 2 at 0826 hours0.00956 days 0.229 hours 0.00137 weeks 3.14293e-4 months . The main unit gen-erator was taken off-line at 0917 hours0.0106 days 0.255 hours 0.00152 weeks 3.489185e-4 months . Leak checking and tube plugging in the 1A Condenser Waterbox was completed at 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months and tne box was returned to service at 1720 hours0.0199 days 0.478 hours 0.00284 weeks 6.5446e-4 months .

January 27 Condenser hotwell drain and fill operations were in progress in an attempt to improve secondary plant chemistry.

Chemistry had improved sufficiently by 0450 hours0.00521 days 0.125 hours 7.440476e-4 weeks 1.71225e-4 months to permit the station to go on-line. The main unit generator was synchronized to the grid at 0707 hours0.00818 days 0.196 hours 0.00117 weeks 2.690135e-4 months . Reactor power was increased slowly due to isolation of 18 and IC Waterboxes for leak checking.

' January 28 Reactor power was being maintained at 80 percent. Leak through- checking and tube plugging of the IC Condenser Waterbox January 31 were completed at 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months on the 28th. The box was placed back in service at 1616 hours0.0187 days 0.449 hours 0.00267 weeks 6.14888e-4 months and a power escalation was begun with the IB Condenser Waterbox still isolated.

The IB Condenser Waterbox was returned to service at 0545 hours0.00631 days 0.151 hours 9.011243e-4 weeks 2.073725e-4 months on the 29th. The 1A Condenser Waterbox was taken out of service at 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months for leak checking.

Reactor power was reduced 10 percent at 0415 hours0.0048 days 0.115 hours 6.861772e-4 weeks 1.579075e-4 months on the 30th due to a high AT across the IB Condenser Waterbox.

The 1A Condenser Waterbox was returned to service at 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months and a reactor power increase was begun at 0642 hours0.00743 days 0.178 hours 0.00106 weeks 2.44281e-4 months .

A nominal 100 percent reactor power was reached at 0900 hcurs on the 30th. Secondary plant chemistry was very much im-proved and the condenser was being monitored regularly for

~ leaks.

I t

MAJOR MAINTENANCE - JANUARY 1984 4

4

1. The .1B Containment Instrument Air Compressor was replaced.

12 2. The IB 'and IC Main Feedwater Flow Regulating Valve Actuators were repaired.

3. The Main Condenser was leak checked with helium, and defective tubes were plugged at various times throughout the month.

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ML20080T893

Text

SUMMARY

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