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Monthly Operating Rept for Jan 1985
	ML20107D724
Person / Time
Site:	Beaver Valley
Issue date:	01/31/1985
From:	Carey J, Smith P; DUQUESNE LIGHT CO.
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8502250130
	Download: ML20107D724 (9)
	v • d • e

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j OPERATIAG DATA REPORT DOCKET NO. 50-334 i-DATE 2/9/85

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COMPLETED BY E.,._A. Smith

'iELEPHONE. 417-4 % 1825 OPERATING STATUS B$ aver Valley Power Station, Unit #1 Notes

!. Unit Name:

2. Reporting Period:

3. Licensed Thermal Power (MWt):

NO

4. Nameplate Rating (Gross MWe):

923

5. Design Electrical Rating (Net MWe):

835

6. Maximum Dependable Capacity (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:

e

9. Power Level To Which Restricted. If Any (Net MWe):

None

10. Reasons For Restrictions.If Any; E/A

'Inis Mondi Yr. to.Dete

' Cumulative

!!. Hours la Reporting Period 744 744 76,752

12. Number Of Hours Reactor Was Critics; 684.1 684.1 38,039.8-

13. Reactor Reserve Shutdown Hours 0-0

-4,482.8

14. Hours Generator On.Line 616.9 616.9

-36,699.8-

!$. Unit Reserve Shutdown Hours 0

0~

'0-

16. Grom Thermal Energy Generated (MWH) 1,230,666 1,230,666 84,629,180

-')

17. Gross Electrical Energy Generated (MWH) 396,000 396,000 26,890.400 i

18. Net Electrical Energy Generated (MWH) 363.040 363.04O' 24.987,883-

19. Unit Service Factor

~82.9-

~82 o 50.0-

20. Unit Availability Factor 82.9 82.9 50.0

21. Unit Capacity Factor (Using MDC Net)

'60.2'

' 60. 2 -

_ r 43.6 -

22. Unit Capacity Factor (Using DER Net)

E8.4 58.4 42.3-

23. Unit Forced Outage Rate 5.7 5.7 26.8'

+

24. Shatdowns Scheduled Over Next 6 Months tType. Dete. sad Ouration of Esch):

N/A

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

26. Units in Test Status (Priei to Commercial Operation):

- Foreenst fAchieved 1 INIT!AL CRITICALITY i N/A N/A -

V

. N.[A.,

N/A INITIAL ELECTRICITY.

(

COMMERCIAL OPERATION N/A N/A-i

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B502250130 850131

\\v PDR ADOCK 05000334

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AVERAGE DAILi UNIT POWER LEVEL DOCKET NO.

50-334 UNIT 3Y?S Unit 71 DATE 2/8/85 COMPLETED BY P. A. Smith TELEPHONE (412) 643 1825 MONTH Januan DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe. Net)

{g y,,g,y 4

1 0

g7 416 0

743 2

gg 455 3

19 7

701 4

20

-5 170 782 gg 375 783 6

22 373 826

-7 33 3

333 93~

,4 293

_9 25 413 413 413 Io y

gg 453 699

+

497 825 12 3

783

' 13 3

14 -

784 825 30 15 824 31

-825 16 498 e

INSTRUCTIONS

,On this format. iist the average daily unit power Ice! in MWe. Net for each day in the' reputting month. Coinpute io the nearest wnvie mepwat1.

I j

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1 UNITSHUTDOWNS AND POWER REDUCTIONS DOCKETNO.

50-334 UNIT NAME BVpS Unit #1 DATE REPORT Af0Niil January 1985 COMPLETED BY

.P.

A.

Smith TELEP110NE (412) 643-1825 "i

.! E.

3

.hY S

Licensee g-t, Cause A Cussesthe N'-

DJ'e y

3?

4 2 i oc Event 33 h3 Atti.m to

$5 sE j di g Repmta A L'

[L' Psevent Recurrente 6

1.

-850101 S

85.5 C

4 N/A ZZ ZZZZZZZ Station remained shutdown for 4th refueling.

2.

850104 S-4.5 B

1 N/A HA TURBIN At 0002 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months on the 4th, the Station was taken off line to perform the scheduled Turbine overspeed Trip Test.

The Station returned to service at 0432 hours0.005 days 0.12 hours 7.142857e-4 weeks 1.64376e-4 months on the 5th.

-~3.

850116 F

17.5 A

3 85-003 CH CKTBRK A Reactor Trip with Safety injection occurred at 1525 hours0.0177 days 0.424 hours 0.00252 weeks 5.802625e-4 months . This was a result of Power Feed Breaker 3-3 from the vital bus to a portion of protection Channel 3 opening.

4, 850118' S.

O B

5 N/A CH PUMPXX A power reduction occurred at 2000 hrs.

on the 18th for seal replacement on th<

Main Feedwater Pump [FW-P-1B].

The pump was returned to service at 0617 hours0.00714 days 0.171 hours 0.00102 weeks 2.347685e-4 months on the 20th, and power was sub-sequently increased.

s ll 2

3 4

- F: F.wsed Reasem:

Hethods Exhibit G. Instrutilims 5: Schededed A Eiguipnient Failure (Explain) 1-Manumt ro, Pseparasi.m of Data B-Meineensoce si Test 2-Manual scre.

Entr> Sheels for IAcmee

- C Refneling.

3-Automatic Scram Evesil Rep *HI Il.I'R I lle INilRI:G D Repdatm> Resilicii'm -

4-Continued From Frevious Month 01611 F4)pessene Training A tiense fixandnael'*

5-Reduction F Adneinherselve '

. G45peratiemal Esone ll:nplaint 9-Other Eshihit 1 - Sanic Souisc

.l'8/77 0 11 Doher (Esplaini

4

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PAGE 2 4

UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-334 UNIT NAME BVPS Unit #1 DATE REPORT MONiil January 1985 COMPLETER) RY P_

A-Rmlth TELErtlONE (412) 643-1825 "t.

a 3

.! E 3

h.Eh 1.kensee E.t.

$4 Cause A Ciuretthe Na'.

D8'e EE 4

2 y ec Event

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%.3 Asti.m to sII j5g McP wl 8' Yi0

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Preveni Recurrente d

5.

850124 P

19.6 A

'1 85-002 CB VALVEX At 0239 hours0.00277 days 0.0664 hours 3.95172e-4 weeks 9.09395e-5 months on the 24th commenced plant shutdown due to loss of seal water to Reactor Coolant Pump IRC-F-1A]

The packing follower on valve CH-184 broke allowing packing to blow-out.

The valve CH-184 was repaired and the Station returned to service at 2310 hours0.0267 days 0.642 hours 0.00382 weeks 8.78955e-4 months on the 24th.

-6.

850125 P

O B

9 N/A CH PUMPXX Power was held at a reduced level so that alignment work could be performed on the IB Main Feedwater Pump.

Work was completed at 2325 hours0.0269 days 0.646 hours 0.00384 weeks 8.846625e-4 months on the 26tr i

s-l 2

3 4

F: F.wced Reasius:

Hethod:

Exhible G. Instint tiims S Scheduleil A-Eiquipment FailureIEmplain) 1-Manua1 fin Pseparati.m of Data 8.Maisitenance ci Test 2-Manuel scree Entr> Sheces I w I.kensee C Refueling 3-Automatic Seras Event Repius 11.8 RIlile INllREG D Regislaetw) Resitisthm 4-Continued From Previous Month 01611

- l'-Opesalen Tsaining A l.icense I:xaminati'*

5-Reduetton C

1 -Adannisleselve 9-Other 5

. G4)peralkmal Espn ll:aplabel Eshsbil 1 SJme Senn (c l/77) -

il Other IEsplshil

'Af Telephone (412) 393-6000 Nuclear Group P.O. Box 4 Shippingport, PA 15077-0004 Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Monthly Operating Report U.

S.

Nuclear Regulatory Commission Director, Office of Management Information & 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, 1985.

Very truly yours, J.

Carey Vice President Nuclear Group rw Enclosures cc: NRC Regional Office King.of Prussia, PA O

I

NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE January 1985 January 1 The Station was in Operation Mode 3,

hot standby.

The Reactor Coolant System temperature and pressure were being increased to normal operating level.

January 2 Normal operating pressure, 2235 psig, and temperature, through 5470F were reached and maintained.

At 0202 hours0.00234 days 0.0561 hours 3.339947e-4 weeks 7.6861e-5 months on January 3 the 2nd, criticality was achieved with Control Bank "D" at 158 steps.

Core Low Power Physics testing was in progress.

January 4 At 0529 hours0.00612 days 0.147 hours 8.746693e-4 weeks 2.012845e-4 months the turbine was latched.

The turbine was tripped at 0817 due to smoke issuing from an area between the

2 Low Pressure Turbine and the Generator.

The smoke occurred due to high temperatures in the seal oil system.

Turbine startup was reintiated at 0920 hours0.0106 days 0.256 hours 0.00152 weeks 3.5006e-4 months .

At 0925 hours0.0107 days 0.257 hours 0.00153 weeks 3.519625e-4 months , the turbine was tripped due to an electrohydraulic system le ak.

Turbine startup recommenced at 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months and the _ turbine-trip test pe rf o rmed at 1231 hours0.0142 days 0.342 hours 0.00204 weeks 4.683955e-4 months ..

During the test an extraction steam non-return valve did not operate properly and retest was scheduled.

At 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months , the Main Unit Generator was synchronized to the grid.

Power level was increased to 20 percent and maintained there for additional testing to be pe rf o rmed.f January 5 At 0002 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months on the 5th, the Main Unit Generator'was taken off line to perform the Turbine Overspeed Trip Test.

The test completed satisfactorily at 0048_ hours and the generator sychronized tofthe grid at 0432 hours0.005 days 0.12 hours 7.142857e-4 weeks 1.64376e-4 months .

3: percent / hour. rate..

Reactor Power was increased at a January 6 Reactor-Power was at a 49 percent hold pointito' perform-a full-core flux cap.

January 7

'The Reactor CoolSnt. System. was at normal operating pressure and temperature at 49

_ percent' power.:

Operations determined Rod F-10 indicator;was reading;1ow by greater than - : 12~ steps-from CBD. Group Demand Counters.

LVeritiention-using fprimary voltage also indicated Rod F-10 was low by g'ceater - than. +

'12{' steps

+

Rod': overstepping from

.CBD LGroup Demand Counters.. confirm that Rod procedure TOP.85-1:waslperformedEto F-10 was in alignment; with ~ the : remaining f rods in its respective ~ group.- Preparation was made to recalibrate the indicator; for. RodEF-10; however, problems with the input test-signal equiment were: encountered.,

1,

January 1985 Summary of Monthly Operating Experience January 8 Equipment to input test signal repaired and Rod F-10 was through recalibrated to i nd i a.a t e proper position.

Reactor Power January 11 was reduced to 30 percent due high steam generator conductivit 7 Individual condenser waterboxes were drained ai.

tubes repaired, as necessary.

Power level was then increased to 60 percent.

Reactor power was being maintained at 60 percent to perform flux maps for calibration of Power Range Detectors N-41, 42, 43 and 44.

January 12 Power level was increased at 3 percent / hour rate.

At through-0530 hours on the 14th power level of 100 percent was January 14 attained.

-January 15 The Station was in Operational Mode 1 at a nominal

'through 100 percent, and the Reactor Coolant System was Lt normal January 16 operating tecperature and pressure.

At 1528 hours0.0177 days 0.424 hours 0.00253 weeks 5.81404e-4 months on the 16th, a rapid drop of_

steam generator level and steam pressure in c o nj un ct io n with a steam flow-feed mismatch caused-a reactor trip with safety injection, i

The problem was attributed to the power feed breaker from vital bus 3 opening.-

January 17 Station in Operational Mode 3.

At 0707 hours0.00818 days 0.196 hours 0.00117 weeks 2.690135e-4 months the reactor was taken critical.

At 0902 hours0.0104 days 0.251 hours 0.00149 weeks 3.43211e-4 months the Main Unit Generator was synched to the grid.

At 2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months the station reached 100 pe rcent nominal power.

. January 18 The Station was in Operational Mode 1 at a nominal through 100 pe rcent power.

Power level was reduced to 60 percent

' January 19 at 2115 hours0.0245 days 0.588 hours 0.0035 weeks 8.047575e-4 months for pe rf o rmance ~ of maidtenance' on Main-Feedwater Pump (FW-P-1Bl.

^

January 20 The Station was in Operational Mode 1 with-Reactor Power-through a nominal 100 percent.

The Reactor Coolant System January-23 was at normal operating temperature and pressure.

-January 24

! At 0239 hour0.00277 days 0.0664 hours 3.95172e-4 weeks 9.09395e-5 months s-commenced plant shutdown dueJto=1oss--of.

seal' water to Reactor-Co o lan t Pump' (RC-P-1A1

>The; Station -was taken

.off.

line at.0331 hours0.00383 days 0.0919 hours 5.472884e-4 weeks 1.259455e-4 months and entered Mode 3 at'0410 hours0.00475 days 0.114 hours 6.779101e-4 weeks 1.56005e-4 months .

.The Reactor was taken critical at 2141 hours0.0248 days 0.595 hours 0.00354 weeks 8.146505e-4 months

~and the Main Unit Generator was synched ~to the' grid at.2310.

January 25 Station in Ope rational ^ Mode 1 and at 55 percent _ power through level.

Maintenance beingJpe rformed on Main Feedwater

~

-January 26 Pump (FW-P-1B1

.2

+

7 m.

January 1985 Summary of Monthly Operating Experience January 27 The Station was in Operational Mode 1 with Reactor Power through at a nominal 100 percent.

Reactor Coolant System was at January 31 normal operating pressure and t em pe r a tur e.

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MAJOR MAINTENANCE - January 1985 1.

Maintenance of Main Feedwater Pump [FW-P- 1 B ]

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ML20107D724

Text

SUMMARY

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