ML19210D145

Revised Monthly Operating Rept for May 1979

ML19210D145
Person / Time
Site:	North Anna
Issue date:	11/05/1979
From:	Wil Madison VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19210D121	List: ML19210D120 ML19210D124 ML19210D125 ML19210D129 ML19210D130 ML19210D131 ML19210D132 ML19210D134 ML19210D137 ML19210D140 ML19210D143 ML19210D144 ML19210D145 ML19210D147 ML19210D150 ML19210D152 ML19210D155
References
NUDOCS 7911200583
Download: ML19210D145 (5)

Text

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VIRGINIA ELECTRIC Af1D POWER COMPANY f;0RTH ANNA POWER STATION MONTHLY OPERATING REPORT MONTH May YEAR 1979 (Revised 11-05-79)

SUBMITTED:

\\D N C c,, 3 -

SUPERINTEi! DENT - OPERATI0flS APPROVED:

/ Add, nr MANAGER \\J 1367 319 7911209 f&3

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gL OPERAllNG DATA REPORT DOCKET No. 50-338 _ _

DATE lh5-79 CO.\\lPLETED liY l!- R fiad.ison TELEPliONE (703-)M4-5151 OPERATING STATUS

1. Unit Name:

North Anna. Unit 1 N<nes

2. Reporting Period.

thy '1979 (Revised)

3. Licenwd Thennal Power (.\\lWt):

777r;

4. Nameplate Rating (Gross 5f We):

9.47

5. Design Electrical Itating (Net 51We):

907

6. Staximum Dependable Capacity (Grow SIWE):

928 898

7. Maximum Dependable Capacity (Net 5f We).

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

l!/A

. N/A

9. Power Level To Which Restrie:ed,if Any (Net MWe)N/A

10. Reawas For Re3trictions,If Any:

This 5f onth

_ Yr..to.Date Cumulatis e

11. IIours la Reporting Period 7,44 3,623 8,610 702.2 2,688.2 7,,735 _,

12. Number Of !!ours Reactor Was Critical TD 48.7 145.5

13. Reactor Reserve Shutdown !!ours I*d 2 'bU 2b _

14. If ours Generator On.Line

15. Unit Reserve Shutdown !!ours 0

O_ _

Q

16. Gross Thermal Energy Generated (MWif) 1,815,,373

17. Grow Elec:rical Energy Generated (MWii) 680,855__

_6,,97_1_,048

]1,1 g,g q _

IS. Net Electrical Energy Generated (MWif) 547,621 2,229 070 f l29dQ7 b

2 2_,10_0,101__ 5.2rd 4Bl_ _

19. Unit Service Factor 90.2 72.1 r /t 1

20. Unit Asailability Factor 90.2 72.1 84.1._

21. Unit Capacity Factor (Usin; MDC Net) 82.0 64.6 74,l__

22. Unit Capacity Factor (Using DER Net) 81.2 63J_

...13_. 6..

23. Unit Forced Outage Rate 6.0 9.3_

_ GJ_

24. Shutdowns Scheduled Over Nnt 6 Months (Type. Date and Duration of Each):

Reserve Station _ Service Tie-in; pos_si_b_ly iluly 1979; 10 days

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

N/A

26. Units in Test Status (Prior to Commercial Operatian):

Forecast Achieved INITI \\ L CRITICAL! rY INITIAL ELECTRICITY COMMERCIAL OPERATION 1367 520 (o/77 )

Page 1 of 2 UNIT SiiUTDOWNS AND POWER REDUCTIONS Dp r

Anna 1

DATE --11-5-79 hWSb REPO R T ',10NIli May 1979 (Revised)

COS[PLET EL p 3

-h1 17

_3Ei Licemee pr, Cause & Correet ne W

Date

• i 2 3

hE3 l' vere v7 E?

Attion to j@

d Report u E0 0

Present Recurrence O

6 79-6 THISSHUTCbWNWASCONCLUDED ON MAY 2, 1979 AT 0445 UHE i THE TURB [NE GENERATOR WAS PLACED IN SERVICE.

DURATION 29.7 HOURS.

79-7 790503 F

14.9 A*

3 NA NA NA Automatic Reactor / Turbine / Generator Trip due to S/G Low level with feed flow / steam flow mismatch. Reason in-sufficient feedwatcr flow when feedpump was tripped due to loss of oil flow.

Repaired broken oil line.

Returned Reactor & Turb. Gen. to service.

79-8 790512 F

26.8 B*

1 NA NA NA Unit shutdown by normal procedure to pdrf,orm 18 mo. periodic test surveillance on the safety injection system & mainte-nance on "C" steam generator level transmitter. Satisfactorily completed 79-9 790513 F

0.0*

G*

1 NA NA NA testing & maintenance.

Reactor trip T

due to operational error in biccking the source range high flux trip above (i.=

permissive P 6. Operator was instructed g uos to obeorvn P 6. Pnnetne ice enc Hrted I N

}

wi 3

4 N

F: Forced Reason:

Method:

Exhibit G -Instructions g

S: Sched u!ed A. Equipment Failure (Explain) 1 -Manual for Preparation of Data B-Maintenance ci Test 2-Manual Scram.

Entry Sheets for Licensee C-Refue!!n r 3-Automatic Scram-Event Report (LER) Fi:e (NUREG-D-Regulatdry Restnetion 4-Ot her ( Explain )

0161)

E-Operator Training & License Examination c22a F-Administratise 5

g G Operational Error (Explain)

Exhibit ! Same Source W/77) li-Othe r ( E xplain )

• See Attached Sheet

Page 2 of 2 0

J[O UNIT SliUTDOWNS AND POWER REDUCTIONS crt na1 DATE 11-5-70 COMPLETED BY U. R. 'iadison REPORT MON 111 May 1979 (Revised)

TELEPliONE _(103) 8%-5151

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Da:e

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j=u frent

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At t n.n to f _:

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Report u Ev Preunt Ree,rrerCe H

v:

6 79-10 790513 F

0.0 G*

1 NA NA NA Turbine /Reacter Trip due to Hi-Hi stm Gen. "B" water level. L'hile attempting, to start up the unit too much water Y

was added to "B" S/G & temp. caused 6

9 the water level to swell to the Hi-Hi

('

9 Level trip point. Restored level &

W restarted the reactor. Instructed operations to feed the S/G carefully, p

9 79-11 790518 F

1.3 G*

3 NA NA NA yeactor/ Turbine / Generator trip from steam flow /fced flow mismatch & low S/G water level. Lost feedpump suction gg pressure when condensate was valved into the flash evaporatcr. The flash y

evaporator was valved out & the reactor g

& turbine generator then placed back in service. Significant couer rcductic b

of 20% of the average daily pcwer leve:y 79-12 790531 NA NA A*

NA NA NA NA

'~~

See Attached sheet.

6 Os N !

2 3

4 F' ForecJ Reason:

Method:

Exhibit G -Instructiens v-S Se edu!cd A Equipment Fa!!ure (Explain) 1 -Manual for Preparation of Data N

B-Maintenance of Test Manual Scram.

Entr> Sheets for I.L. see N

C-Re :eling 3 Automatic Scram.

E.ent Report (LER) Filz (NUREG.

r D Regalatery Restriction 4-Other ( E xrtain )

0161)

E-Operator Training & License Examination F-Administ rative 5

G-Operational Error (Explain)

Estubit ! Same Source (9/77)

!!-Ot her ( Explain )

Note: Number 79-11 continues into the month of June 1979 (Significant power level reduction)

Page 1

of 1

UtlIT SiluTDOWN AND POWER REDUCTIONS EXPLAMATION SHEET DOCKET fl0.

50-333 REPORT MONTH thy (PerisedylIT fiAME tiorth Anna YEAR 1979 DATE 11-5-79 COMPLETED BY W. R. t%DISON 79-7 (A)

A broken oil line to the (B) Feed Pump flotor caused a low oil pressure trip of the feed pump.

79-8 (B)

As an initial condition of 1-PT-83.1 and 1-PT-83.2 (Simulated blackout and safety injection of 1H and lJ busses, the unit was removed from service and the reactor shutdown to Mode 3, during the shutdown maintenance was performed on "C" S/G level transmitter.

78-9 (G)

Unit was not in service.

In the course of a Rx startup, the operator failed to block the source range high flux Rx Trip (PG).

79-10 (G)

Turbine Trip / Reactor trip when too much water was added to the steam generators causing "B" S/G to swell to the !!i-Hi Level Trip point.

79-11 (G)

Reactor / Turbine / Generator Trip from steam flow / Feed flow mismatch and low S/G water level.~ When condensate was valved into the flash evaporator to increase plant performance, differential pressure created across the heat exchanger caused feedpump suction press to decrease causing feed flow to decrease to the point where S/G level could not be maintained.

79-12 A High bearing temperature on "C" main feedpump required a reduction in megawatt load when the feedpump was removed from service.

1367 123