ML19273B911: Difference between revisions
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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION MONTHLY OPERATING REPORT MONTH May YEAR 1979 SUBMITTED: | VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION MONTHLY OPERATING REPORT MONTH May YEAR 1979 SUBMITTED: | ||
ND\ %h SUPERIIIID1 DENT - OPERATIONS ~ | ND\ %h SUPERIIIID1 DENT - OPERATIONS ~ | ||
APPROVED: | APPROVED: | ||
/ | / | ||
/ t/ | / t/ | ||
MANAGER ( | MANAGER ( | ||
2354 047 7906180//93i | 2354 047 7906180//93i | ||
OPERATING DATA REPORT DOCKET NO. 50-338 DATE 6-4-19 COMPLETED BY Ll P Mariison TELEPHONE 701-R04-5151 OPERATING STATUS North Anna, Unit 1 Notes | OPERATING DATA REPORT DOCKET NO. 50-338 DATE 6-4-19 COMPLETED BY Ll P Mariison TELEPHONE 701-R04-5151 OPERATING STATUS North Anna, Unit 1 Notes | ||
: 1. Unit Name: | : 1. Unit Name: | ||
Line 34: | Line 31: | ||
: 2. Reporting Period: | : 2. Reporting Period: | ||
27lb | 27lb | ||
: 3. Licensed Thermal Power (MWt): ' | : 3. Licensed Thermal Power (MWt): ' | ||
: 4. Nameplate Rating (Gross MWe): .. | : 4. Nameplate Rating (Gross MWe): .. | ||
Line 43: | Line 39: | ||
N/A | N/A | ||
: 9. Power Level To which Restricted. If Any (Net MWe): N/A | : 9. Power Level To which Restricted. If Any (Net MWe): N/A | ||
: 10. Reasons For Restrictions,if Any: N/4 | : 10. Reasons For Restrictions,if Any: N/4 This Month Yr..to.Date Cumulative | ||
: 11. Hours in Reporting Period 744 3.624__ 8,641 702.2 2,688.2 7,735 | |||
This Month Yr..to.Date Cumulative | |||
: 11. Hours in Reporting Period 744 3.624__ 8,641 | |||
702.2 2,688.2 7,735 | |||
: 12. Number Of Hours Reactor Was Critical | : 12. Number Of Hours Reactor Was Critical | ||
: 13. Reactor Reserve Shutdown Hours 11.8 11.8 11,8 671.3 2,611.2 7.262.9 | : 13. Reactor Reserve Shutdown Hours 11.8 11.8 11,8 671.3 2,611.2 7.262.9 | ||
Line 57: | Line 47: | ||
: 16. Gross Thermal Energy Generated (MWH) 1.81R.371 6 971 nap 19.167.843 | : 16. Gross Thermal Energy Generated (MWH) 1.81R.371 6 971 nap 19.167.843 | ||
: 17. Gross Electrical Energy Generated (MbH) 6P0.95~ _ _ . ? ??n nin A 17o_Rn7 | : 17. Gross Electrical Energy Generated (MbH) 6P0.95~ _ _ . ? ??n nin A 17o_Rn7 | ||
: 18. Net Electrical Energy Generated (MWH) 5d7.6?1 2.100.9n1 6:7gg 491 | : 18. Net Electrical Energy Generated (MWH) 5d7.6?1 2.100.9n1 6:7gg 491 | ||
: 19. Unit Service Factor 90.2 72.1 R4 1 | : 19. Unit Service Factor 90.2 72.1 R4 1 | ||
Line 64: | Line 53: | ||
: 22. Uni Capacity Factor (Using DER Net) 81.2 61 9 _ 73.6 | : 22. Uni Capacity Factor (Using DER Net) 81.2 61 9 _ 73.6 | ||
: 23. Unit Forced Outage Rate 9.R 26.6 12.1 | : 23. Unit Forced Outage Rate 9.R 26.6 12.1 | ||
.- 24. Shutdowns Scheduled Over Nest 6 Months (Type. Date, and Duration of Each t: | .- 24. Shutdowns Scheduled Over Nest 6 Months (Type. Date, and Duration of Each t: | ||
Reserve Station Service Tie-in; possibly Julv 1979; 10 days | Reserve Station Service Tie-in; possibly Julv 1979; 10 days | ||
: 25. If Shur Down At End Of Report Period. Estimated Dare of Startup: N/A | : 25. If Shur Down At End Of Report Period. Estimated Dare of Startup: N/A | ||
: 26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved | : 26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMM ERCIAL OPERATION 2354 048 | ||
INITIA L CRITICALITY INITIAL ELECTRICITY COMM ERCIAL OPERATION 2354 048 | |||
("/77) | ("/77) | ||
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-338 UNIT NA 1 DATE 6/4/79 | |||
AVERAGE DAILY UNIT POWER LEVEL | - COMPLETED BY tt D . M a d i c,on TELEPHONE 703-894-5151 MONm May 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 37 837-2 590 33 756 819 837 3 ,, | ||
4 258 ,o 836 5 818 21 837 6 836 3, 832 831 ,g 831 7 | |||
DOCKET NO. 50-338 UNIT NA 1 DATE 6/4/79 | |||
- COMPLETED BY tt D . M a d i c,on TELEPHONE 703-894-5151 | |||
MONm May 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 37 837-2 590 33 756 | |||
819 837 3 ,, | |||
4 258 ,o 836 5 818 21 837 6 836 3, 832 | |||
831 ,g 831 7 | |||
811 828 3 | 811 828 3 | ||
820 830 9 25 to 835 26 827 gi 835 839 3 | 820 830 9 25 to 835 26 827 gi 835 839 3 | ||
776 , 841 13 0 29 839 34 718 3o 763 15 832 3, 670 836 16 | |||
776 , 841 13 0 29 839 | |||
34 718 3o 763 15 832 3, 670 836 16 | |||
. 2354'0'49 INSTRUCTIONS On t!us format, hst the average dady unit power level in MWe-Net for each day in the repomng month. Cornpute to the nearest whoie rnegswatt. | . 2354'0'49 INSTRUCTIONS On t!us format, hst the average dady unit power level in MWe-Net for each day in the repomng month. Cornpute to the nearest whoie rnegswatt. | ||
(9/77) | (9/77) | ||
Page 1 of 2 ; | Page 1 of 2 ; | ||
DOCKET NO. 50-338 UNIT S!!UTDOWNS AND POWER REDUCTIONS UNif NAME North Anna 1 DA'IE tlyne 1, 1979 COMPLETED BY A G _ P o u fg.__ | DOCKET NO. 50-338 UNIT S!!UTDOWNS AND POWER REDUCTIONS UNif NAME North Anna 1 DA'IE tlyne 1, 1979 COMPLETED BY A G _ P o u fg.__ | ||
May 1979 REPORT MONTil TELFPilONE 707-994 El'il x 229 ' | May 1979 REPORT MONTil TELFPilONE 707-994 El'il x 229 ' | ||
h 2 | h 2 | ||
-" En Cause i Coirec tive | -" En Cause i Coirec tive | ||
- EO #E Licensee E''t I No. Dale (, j! k ) (E[C Event wL f'8u Action to Psevent itecumence t-fI 5 j gp, g lleport # g 6 | - EO #E Licensee E''t I No. Dale (, j! k ) (E[C Event wL f'8u Action to Psevent itecumence t-fI 5 j gp, g lleport # g 6 | ||
79-5 THIS SHUTD( WN W .S C0flCL JDED ' )N MAY d, 1979 AT 04l 5 UHEt, THE TURB NE GENERATOR WAS PLACED I!! SERVICE. | 79-5 THIS SHUTD( WN W .S C0flCL JDED ' )N MAY d, 1979 AT 04l 5 UHEt, THE TURB NE GENERATOR WAS PLACED I!! SERVICE. | ||
DURATI0fl 2t .7 HOURS. | DURATI0fl 2t .7 HOURS. | ||
Line 119: | Line 86: | ||
E-Operator Trainingi License Examination F. Administrative 5 G-Ope <ational Luor (Explain) Eshibis 1 Same Sonree (9/77) 11 Other (Explain) | E-Operator Trainingi License Examination F. Administrative 5 G-Ope <ational Luor (Explain) Eshibis 1 Same Sonree (9/77) 11 Other (Explain) | ||
*See Attached Sheet - | *See Attached Sheet - | ||
Page 2 of 2 i l | Page 2 of 2 i l | ||
DOCKET NO. 50-33R l UNIT S!!UTDOWNS AND POWER REDUCTIONS UNir N AME North Arc 3 1 i DATE June 1. 1979 ,i REPORT MONTil May 1979 COMPLETED BY A G N m i fe r TELEPilONE 703-894-5151 x 229 i | DOCKET NO. 50-33R l UNIT S!!UTDOWNS AND POWER REDUCTIONS UNir N AME North Arc 3 1 i DATE June 1. 1979 ,i REPORT MONTil May 1979 COMPLETED BY A G N m i fe r TELEPilONE 703-894-5151 x 229 i | ||
Line 129: | Line 94: | ||
' " *# "" "I '' # | ' " *# "" "I '' # | ||
7 | 7 | ||
* E | * E No. Da t t- p. e$o 4 532: l* CHI G? | ||
No. Da t t- p. e$o 4 532: l* CHI G? | |||
AG G3u Attiun to | AG G3u Attiun to | ||
* 8,3 5 j5g Itepott 8/ Present llecurrence 6 | * 8,3 5 j5g Itepott 8/ Present llecurrence 6 | ||
Line 137: | Line 100: | ||
Gen. "B" water level. While attemptin ; | Gen. "B" water level. While attemptin ; | ||
to start up the unit too much water w as added to "B" S/G & temp. caused the w ;ter level to swell to the Hi-Hi Level tri 3-point. Restored level & restarted the reactor, instructed operations to feed the S/G carefully. | to start up the unit too much water w as added to "B" S/G & temp. caused the w ;ter level to swell to the Hi-Hi Level tri 3-point. Restored level & restarted the reactor, instructed operations to feed the S/G carefully. | ||
79-10 790518 F 1.3 G* 3 ilA NA Nf. Reactor / Turbine / Generator trip from steam flow / feed flow mismatch & low S/G water level. Lost feedpump suctic o i pressure when condensate was valved i .to i | 79-10 790518 F 1.3 G* 3 ilA NA Nf. Reactor / Turbine / Generator trip from steam flow / feed flow mismatch & low S/G water level. Lost feedpump suctic o i pressure when condensate was valved i .to i the flash evaporator. The flash evapo ator was valved out & the reactor & turbin - | ||
the flash evaporator. The flash evapo ator was valved out & the reactor & turbin - | |||
generator then placed back in service . | generator then placed back in service . | ||
79-11 790531 NA NA A* NA NA NA NA Significant ' power reduction of 20% of the average daily power level. | 79-11 790531 NA NA A* NA NA NA NA Significant ' power reduction of 20% of the average daily power level. | ||
Line 148: | Line 109: | ||
NOTE: Number 79-11 continues into the month of June 1979 (Significant power level reduction) f | NOTE: Number 79-11 continues into the month of June 1979 (Significant power level reduction) f | ||
, Page 1 of 1 UNIT SHUTDOWN AND POWER REDUCTIONS EXPLANATION SHEET DOLXET NO. 50-338 REPORT MONTH May UNIT NAME North Anna 1 YEAR 1979 DATE June 1,1979 COMPLETED BY A. G. Neufer 79-6 (A) A broken oil line to the (B ) Feed Pump Motor caused a low oil pressure trip of the feed pump. | , Page 1 of 1 UNIT SHUTDOWN AND POWER REDUCTIONS EXPLANATION SHEET DOLXET NO. 50-338 REPORT MONTH May UNIT NAME North Anna 1 YEAR 1979 DATE June 1,1979 COMPLETED BY A. G. Neufer 79-6 (A) A broken oil line to the (B ) Feed Pump Motor caused a low oil pressure trip of the feed pump. | ||
79-7 (B) As an initial condition of 1-PT-83.1 and 1-PT-83.'.t (Simulated blackout and safety injection of lH and 11 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. | 79-7 (B) As an initial condition of 1-PT-83.1 and 1-PT-83.'.t (Simulated blackout and safety injection of lH and 11 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. | ||
78-8 (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). | 78-8 (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). | ||
79-9 (G) Turbine Trip / Reactor trip when too much water was added to the steam generators causing "B" S/G to swell to the Hi-Hi Level Trip point. | 79-9 (G) Turbine Trip / Reactor trip when too much water was added to the steam generators causing "B" S/G to swell to the Hi-Hi Level Trip point. | ||
79-10 (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 | 79-10 (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 naintained. | ||
where S/G level could not be naintained. | |||
79-11 A High bearing temperature on "C" main feedpump required a reduction in magawatt load when the feedpump was removed from service. | 79-11 A High bearing temperature on "C" main feedpump required a reduction in magawatt load when the feedpump was removed from service. | ||
2354 052 | 2354 052 I | ||
I | |||
.}} | .}} |
Latest revision as of 18:55, 1 February 2020
ML19273B911 | |
Person / Time | |
---|---|
Site: | North Anna ![]() |
Issue date: | 06/04/1979 |
From: | Wil Madison VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
To: | |
Shared Package | |
ML19273B910 | List: |
References | |
NUDOCS 7906180493 | |
Download: ML19273B911 (6) | |
Text
. .
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION MONTHLY OPERATING REPORT MONTH May YEAR 1979 SUBMITTED:
ND\ %h SUPERIIIID1 DENT - OPERATIONS ~
APPROVED:
/
/ t/
MANAGER (
2354 047 7906180//93i
OPERATING DATA REPORT DOCKET NO. 50-338 DATE 6-4-19 COMPLETED BY Ll P Mariison TELEPHONE 701-R04-5151 OPERATING STATUS North Anna, Unit 1 Notes
- 1. Unit Name:
lay 1979
- 2. Reporting Period:
27lb
- 3. Licensed Thermal Power (MWt): '
- 4. Nameplate Rating (Gross MWe): ..
- 5. Design Electrical Rating (Net MN): 907
- 6. Maximum Dependable Capacity (Gross MWe): 928
- 7. Maximum Dependable Capacity (Net MWe): 898
- 8. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Imt Report. Give Reasons:
N/A
- 9. Power Level To which Restricted. If Any (Net MWe): N/A
- 10. Reasons For Restrictions,if Any: N/4 This Month Yr..to.Date Cumulative
- 11. Hours in Reporting Period 744 3.624__ 8,641 702.2 2,688.2 7,735
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 11.8 11.8 11,8 671.3 2,611.2 7.262.9
- 14. Hours Generator On-Line
- 15. Unit Reserve Shutdown Hours 0 0 n
- 16. Gross Thermal Energy Generated (MWH) 1.81R.371 6 971 nap 19.167.843
- 17. Gross Electrical Energy Generated (MbH) 6P0.95~ _ _ . ? ??n nin A 17o_Rn7
- 18. Net Electrical Energy Generated (MWH) 5d7.6?1 2.100.9n1 6:7gg 491
- 19. Unit Service Factor 90.2 72.1 R4 1
- 20. Unit Availability Factor 90.2 72.I 84.1
- 21. Unit Capacity Factor (Using MDC Net) R?.0 64.6 74.3
- 22. Uni Capacity Factor (Using DER Net) 81.2 61 9 _ 73.6
- 23. Unit Forced Outage Rate 9.R 26.6 12.1
.- 24. Shutdowns Scheduled Over Nest 6 Months (Type. Date, and Duration of Each t:
Reserve Station Service Tie-in; possibly Julv 1979; 10 days
- 25. If Shur Down At End Of Report Period. Estimated Dare of Startup: N/A
- 26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMM ERCIAL OPERATION 2354 048
("/77)
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-338 UNIT NA 1 DATE 6/4/79
- COMPLETED BY tt D . M a d i c,on TELEPHONE 703-894-5151 MONm May 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 37 837-2 590 33 756 819 837 3 ,,
4 258 ,o 836 5 818 21 837 6 836 3, 832 831 ,g 831 7
811 828 3
820 830 9 25 to 835 26 827 gi 835 839 3
776 , 841 13 0 29 839 34 718 3o 763 15 832 3, 670 836 16
. 2354'0'49 INSTRUCTIONS On t!us format, hst the average dady unit power level in MWe-Net for each day in the repomng month. Cornpute to the nearest whoie rnegswatt.
(9/77)
Page 1 of 2 ;
DOCKET NO. 50-338 UNIT S!!UTDOWNS AND POWER REDUCTIONS UNif NAME North Anna 1 DA'IE tlyne 1, 1979 COMPLETED BY A G _ P o u fg.__
May 1979 REPORT MONTil TELFPilONE 707-994 El'il x 229 '
h 2
-" En Cause i Coirec tive
- EO #E Licensee Et I No. Dale (, j! k ) (E[C Event wL f'8u Action to Psevent itecumence t-fI 5 j gp, g lleport # g 6
79-5 THIS SHUTD( WN W .S C0flCL JDED ' )N MAY d, 1979 AT 04l 5 UHEt, THE TURB NE GENERATOR WAS PLACED I!! SERVICE.
DURATI0fl 2t .7 HOURS.
79-6 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 feed water flow v. hen feed-pump was tripped due to loss of oil flow. Repaired broken oil line.
Returnrd Reactor & Turb. Gen.to servit e.
79-7 790512 F 26.8 B* 1 NA NA NA Unit shutdown by normal procedure to perform 18 mo. periodic test surveil-lance on the safety injection system
& maintenance on "C" steam generator level transmitter. Satisfactorily completed testing & maintenance.
N 79-8 790513 F 0.0* G* 1 NA NA NA Reactor trip due to operational error u in blocking the source range high flux trip
'> above permissive P-6. Operator was A instructed to observe P-6. Reactor wr- restarted.
3 4 O I 2 Lyt F: Forced Iteason: Method: Exhibit G -Instructions A fijuipment failure (Explain) 1-Manual for Preparation of Data a S: Scheduled 2 Manual Scram. Entry Shecis for 1.icensee 11-Maintenance or Test C Refueling 3 Automatic Scram. Event Itepois (Ll R) File (NUltLG.
D-Itegulatory Resitiction 4-Other (Explam) 0161)
E-Operator Trainingi License Examination F. Administrative 5 G-Ope <ational Luor (Explain) Eshibis 1 Same Sonree (9/77) 11 Other (Explain)
- See Attached Sheet -
Page 2 of 2 i l
DOCKET NO.50-33R l UNIT S!!UTDOWNS AND POWER REDUCTIONS UNir N AME North Arc 3 1 i DATE June 1. 1979 ,i REPORT MONTil May 1979 COMPLETED BY A G N m i fe r TELEPilONE 703-894-5151 x 229 i
I
. "b -
c_ ri 3: , 5
' " *# "" "I #
7
- E No. Da t t- p. e$o 4 532: l* CHI G?
AG G3u Attiun to
- 8,3 5 j5g Itepott 8/ Present llecurrence 6
79-9 790513 F 0.0 G* 1 NA flA NA Turbine / Reactor Trip due to Hi-Hi stm .'
Gen. "B" water level. While attemptin ;
to start up the unit too much water w as added to "B" S/G & temp. caused the w ;ter level to swell to the Hi-Hi Level tri 3-point. Restored level & restarted the reactor, instructed operations to feed the S/G carefully.
79-10 790518 F 1.3 G* 3 ilA NA Nf. Reactor / Turbine / Generator trip from steam flow / feed flow mismatch & low S/G water level. Lost feedpump suctic o i pressure when condensate was valved i .to i the flash evaporator. The flash evapo ator was valved out & the reactor & turbin -
generator then placed back in service .
79-11 790531 NA NA A* NA NA NA NA Significant ' power reduction of 20% of the average daily power level.
See attached sheet.
N u 1 2 3 4 m F: Fuced Iteasort: Method: Exhibit G . instnieiions y 5: Scheduled A Equipment Failure (Explain), 14f anual for Preparation of Data U4taintenance of Test 2 Alanual Scram- Entr> Sheets for Licemee g C Itefuchng 3 Automatic Sc Jm. Event Iteport (LLk) Fde (NUltLG-D-Itegulatory itestriction 4-Oiher ( Explain) 0161)
~
E. Operator Trainingi License Examination F Administsalive 5 G Operational Eirus (Explain) Estiibiti Same Source r2/77) ll-Ot het (E xplain) l, t
NOTE: Number 79-11 continues into the month of June 1979 (Significant power level reduction) f
, Page 1 of 1 UNIT SHUTDOWN AND POWER REDUCTIONS EXPLANATION SHEET DOLXET NO. 50-338 REPORT MONTH May UNIT NAME North Anna 1 YEAR 1979 DATE June 1,1979 COMPLETED BY A. G. Neufer 79-6 (A) A broken oil line to the (B ) Feed Pump Motor caused a low oil pressure trip of the feed pump.
79-7 (B) As an initial condition of 1-PT-83.1 and 1-PT-83.'.t (Simulated blackout and safety injection of lH and 11 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.
78-8 (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).
79-9 (G) Turbine Trip / Reactor trip when too much water was added to the steam generators causing "B" S/G to swell to the Hi-Hi Level Trip point.
79-10 (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 naintained.
79-11 A High bearing temperature on "C" main feedpump required a reduction in magawatt load when the feedpump was removed from service.
2354 052 I
.