ML19321A029

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for June 1980
ML19321A029
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/15/1980
From: Merson S
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19321A024 List:
References
NUDOCS 8007220355
Download: ML19321A029 (18)
v • d • e


Text

. _ _ _ _ _ _ -_

O OPERATING DATA REPORT DOCKET NO. 50-317 DATE 7/15/80 COMPLETED BY S. D. Merson TELEPHONE 101 214-5240 OPERATING STATUS Calvert Cliffs No. 1 Notes

1. Unit Name:
2. Reporting Period; hne . toro
3. Licensed Thermal Power (MWt): 2.700
4. Nameplate Rating (Gross MWe): 918
5. Design Electrical Rating (Net MWe): 845
6. Maximum Dependable Capacity (Gross MWe): .C
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):
10. Reasons For Restrictions.lf Any:

This Month Yr. to Date Cumulative

11. Hours in Reporting Period 720.0 4,367.0 45,132.0
12. Number Of Hours Reactor Was Critical 720.0 3,803.0 36,242.6
13. Reactor Reserve Shutdown Hours 0.0 38.3 1,098.8
14. Hours Generator On Line 720.0 3,733.6 35,435.6 _
15. Unit Reserve Shutdown llours 0.0 0.0 _

0.0

16. Gross Thermal Energy Generated IMWH) 1,833,401 8,629,179 83,966.168 . l
17. Gross Electrical Energy Generated (MWHi 575J57,_, 2,724,149 27,536,679
18. Net Electrical Energy Generated (MWH) 549,545 2,583,776 26,232,982  ;
19. Unit Service Factor 100.0 85.5 78.5 T
20. Unit Availability Factor 100.0 85.5 78.5
21. Unit Capacity Factor (Using MDC Neti 94.2 73.0 _

71.8

22. Unit Capacity Factor (Using DER Net) 90.3 70.0 68.8
23. Unit Forced Outage Rate 0.0 4.9 8.6
24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Eacht:

No. 1 Plant scheduled for a planned outage starting 10/17/80 until 12/15/80 for refueling, unit general inspection and TMI Modification.

25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY j INITIAL ELECTRICITY l l

COMMERCIAL OPERATION ,,

(9/77) 800722o35$

OPERATLNG DATA REPORT DOCKET NO. 50-318 DATE 7-is_80 COMPLETED BY 9. D. Merson l

TELEPHONE ent_ m 5240 OPERATING STATUS Calvert Cliffs No. 2 Notes

1. Unit Name:
2. Reporting Period: Nu- t9An
3. Licensed Thermal Power (MWt): 2 700
4. Nameplate Rating (Gross MWeb "Il
5. Design Electrical Rating (Net MWe): 845
6. Maximum Dependable Capacity (Gross MWel: A6n l
7. Maximum Dependable Capacity (Net MWe): 825 j
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gi+e Reasons:
9. Power Level To which Restricted. lf Any (Net MWe):
10. Reasons For Restrictions.lf Any:

1 This Month Yr.-to-Date Cumulative 720.0 4,367.0 28,487.0 '

11. Hours In Reporting Period
12. Number Of Hours Reactor Was Critical 720.0 4.127.8 24,072.7
13. Reactor Resene Shutdown Hours 0.0 9.5 422.6
14. Hours Generator On Line 720.0 4.102.0 23,710.5
15. Unit Reserve Shutdown flours 0.0 0.0 0.0 1,869,379 10,658,483 58,902,715 l
16. Gross Thermal Energy Generated (L 'H) .
17. Gross Electrical Energy Generated (MWH) 609,343 _,

3,559,297 _ gj 564,120  !

18. Net Electrical Energy Generated (MWH) _ 583.087 3,405.576 . !',,662,590 l
19. Unit Service Factor 100.0 93.4 83.2 l
20. Unit Availability Factor 100.0 93.9 83.2
21. Ur.t Capacity Factor (Using MDC Net) 98.2 94.5 80.3 *

,22. Unit Capacity Factor IUsing DER Net) os A 02.3 77.5

23. Unit Forced Outage Rate 0.0 0.9 6.0
24. Shutdowns Scheduled 0,er Next 6 Months (Type. Date,and Duration of Eacht:

l

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

l

26. Units in Test Status (Prior o Commercial Operation): Forecast Achieved i INITIAL CRITICALITY j INITIAL ELECTRICITY l COMMERCIAL OPERAT'ON
  • The Maximum Dependable C'apacity taed to calculate the Cummulative to Date Unit Cap.

Factor had to be proportioned, t.hi. h equates to 816.3 MWH. (9/77) 1 l

l

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-317 UNIT Calvert Cliffs #1 DATE 7/15/80 COMPLETED BY S. D. Merson TELEPHONE 301-234-5240 MONTH June. 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net s g 815 g7 814 2 816 gg 674 813 g, 698 3

4 806 20 817 5

7'I 21 819 710 699 6 22 7 767 23 726 g 782 24 788 9 634 25 816' 647 780 10 - 26 33 762 27 815 779 012 12 28 13 715 29 698 14 775 30 813 15 818 3; j 16 740 l

l INSTRUCTIONS On this format, list the average daily unit power levelin MWe. Net for each day in the reporting month. Compute to the nearest whole megawait.

(9/771 1

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-318 gggy Calvert Cliffs #2 DATE 7/15/80 COMPLETED BY 9. n. Merson TELEPHONE 301-234-5240 MONTH June, 1980 DAY AVER AGE DAILY POWER LEVEL DAY 4.iR AGE DAILY POWER LEVEL (MWe Net) (MWe-Net) 844 777 g g7 843 gg 834 2

831 g9 836 3

4 788 20 760 826 802

$ g 6 836 22 037 7 At6 23 840 8 785 24 839 9 832 25 841' 10 832 26 838 gg 831 27 837 12 826 28 833 13 812 29 823 p 835 835 30 15 648 3g 16 580 INSTRUCTIONS On this format. fist the average daily unit power levelin MWe Net for each day in the reportirig month. Compute to the nearest whole megaw:tt.

(9/77) 1

DOCKET NO.

50-317 UNITSHUTDOWNS AND POWER REDUC 110NS UNIT NAME calvere ciiffs #1 DATE 7/15/R0 COMPLETED BY <- n_ w renn REPORT MONTH Inne - 1480 TELEPHONE 301-234-5?40 e.

.$ 'E 3 Y4 Licensee Ev,  % Cause & Corrective No. Date k 5g i 255 Event g? g3 Action to H

$E 5 jig Repost 8 mV g' Prenni Recurrence c5 No outages or reductions.

m i 2 3 4 F: Forced Reason: Method: Exhibit G - Inst ructions S: Scheduled A-Equipment Failure (Explain) I-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entry Sheets for Lkinsee C. Refueling 3-Autonutic Scram. Event ReporI (LER) File INUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Exandnation F Administrative 5 G-Operational Error IExplain) Exhibit I Sanw Source 19/77) llother (Explain)

- ~ ~ _ . _ . . - .

N NO. 50-318 UNITSHUTDOWNS AND POWER REDUCTIONS UNITNAME calvert cliffs #2 DATE 7/15/HO

s. p. Herson COMP 1.ETED BY REPORT MONTH June. 1980 TELEPHONE 301-234-5240 l

n.

- E 5

.$E 3 yYE Licensee ,Ev, g*. Cause & Corrective No. Date k 3g ( jgy Event g'ir 5.] Action to

  • $E 5 jgg Reporia mV Prevent Recurrence d

80-03 800615 F 48.0 A 5 PUNPXX Various forced reductions to repair No. 22 steam generator feed pump.

~

I 4

I 2 3 4 F: Forced Reason: Method: Exhibit G . Instructions S: Scheduled A-Equipment Failure (Explain) I-Manual for Preparation of Data .

1 B Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C Refueling 3-Autunutic Scram. Event ReporI (LER) File (NUREG. ,

, D Regulatory Restriction 4- Cont inua tion 0161)

*perator Training & License Examination 5-Load Reduction F dnunistrative 9-Other 5 Aerational Error (Explain) Exhibit I-Same Source

] (9/77)

. vher (Explain)

7/10/80 REFUELING INFORMATION REQUEST

1. Name of Facility: Calvert Cliffs Nuclear Power Plant, Unit No. 1
2. Scheduled date for next Refueling Shutdown: October 17, 1980
3. Scheduled date for restart follows. J refueling: November 27, 1980*
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Resumption of operation after refueling will require changes to Technical Specifications. The changes will be such as to allow operation of the plant with a fresh reload batch and reshuffled Core.

5. Scheduled date(s) for submitting proposed licensing action and supporting information.

August 29, 1980*

6. Important licensing considerations associated with the refueling.

Reload fuel will be similar to that reload fuel inserted into the previous cycle.

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 217 (b) 364

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

1056 Licensed 728 Currently Installed ,

774 Licensed Addition is Planned

9. The projected date of the last refueling that can be discharged to I the Spent Fuel Pool assuming the present licensed capacity.

October, 1983

  • Information has changed since last month.

7/10/80 REFUELING INFORMATION RE00EST .

1. Name of Facility: Calvert Cliffs Nuclear Power Plant, Unit No. 2.
2. Scheduled date for next refueling shutdown: January 1,1981
3. Scheduled date for restart following refueling: February 12, 1981*
4. Will refueling or resumption of operation thereafter require a technical specification change or other licensed an.endment?

Resumption of operation after refueling will require changes to Technical Specifications. The changes will be such as to allow operation of the plant with a fresh reload batch and reshuffled Core.

5. Scheduled date(s) for submitting proposed licensing action and supporting information.

November 14, 1980*

6. Important .icensing considerations associated with refueling.

Reload fuel will be similar to that reload fuel inserted in the previous cycle.

7. The number of fuel assemblies (a) in the core and (b) in the Spent Fuel Storage Pool.

(a) 217 (b) 364

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been required or is pl< ned, in number of fuel assemblies.

1056 Licensed 728 Currently Installed 774 Licensed Addition is Planned

9. The projected date of the last refueling that can be discharged to the Spent Fuel Pool assuming the present licensed capacity.

October, 1983

  • Information has changed since last month.

SUfEARY OF UtlIT 1 OPERATIflG EXPERIEilCE - jut!E 1980 6/1 At the beginning of this reporting period Unit 1 was operating at 860 MWe with the reactor at 100% power. Operated at reduced load (745 MWe) at 0100 while testing main turbine control valves.

Resumed full load operation (860 MWe)at 0300.

6/5 At 1100 load wa:: reduced to 645 MWe to investigate saltwater leakage into the main conde:nser. Load was increased to 845 MWe at 2200.

6/6 At 0130 load was reduced to 750 MWe to investigate saltwater leakage into the main condenser.

6/7 Load was increased to 825 MWe at 0930 after plugging two condenser tubes. Load was limited to 825 MWe for variable Tave testing.

6/8 At 2140 load was reduced to 715 MWe to investigate saltwater leakage into the main condenser.

6/9 Load was further reduced to 620 MWe due to shear pin failures on

  1. 12A and #12B Travelling Screens which resulted in approaching the ETS 12 F limit on main condenser circulating water AT.

At 1400 load was limited to 665 MWe to investigate saltwater leakage into the main condenser.

6/11 After plugging two condenser tubes resumed f'111 load operation (850 MWe) at 1040. At 2345 load was decrear.ed to 680 MWe to clean condenser water boxes.

6/12 Load was increased to capacity (845 MWe) at 0600. At 2230 load was reduced to 765 MWe to investigate saltwater leakage into the main condenser.

6/13 Load was further reduced to 695 MWe to limit the stress on #138 waterbox while investigating saltwater leakage into the main condenser.

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE - JUNE 1980 6/14 Increased load to capacity (845 MWe) at 0900 after plugging one condenser tube.

6/16 At 1000 load was reduced to 685 fMe to investigate saltwater leakage into the main condenser. Load was increased to 845 MWe when Indications of saltwater leakage disappeared at 2145.

6/18 At 0730 load was reduced to 640 MWe to investigate saltwater leakage into the main condenser.

6/20 Located and plugged one leaking condenser tube. Resumed full load operation (845 MWe) at 0001.

6/22 At 0700 load was decreased to 640 MWe to repair #12 Sluice Gate and #12 Heater Drain Pump. Resumed full load operation (845 MWe) at 2359, 6/23 At 1045 load was reduced to 695 MWe to investigate saltwater leakage into the main condenser.

6/24 Load was increased to 850 MWe at 0830 when indications of salt-water leakage disLppeared.

6/26 At 0600 load was reduced to 670 MWe to investigate saltwater leakage into the main condenser. Load was increased to 845 MWe at 1045 when indications of saltwater leakage disappeared.

6/29 At 0030 load was reduced to 725 MWe to investigate saltwater leakage into the main condenser. Load was increased to 850 MWe at 2100 when indications of saltwater leakage disappeared.

6/30 At the end of this reporting period Unit I was operating at 850 PMe with the reactor at 100% power.

4

SUMMARY

OF UNIT 2 OPERATING EXPERIENCE - JUf!E 1980 6/1 At the beginning of this reporting period Unit 2 was operating at 885 MWe with the reactor at 100% power.

6/3' At 2200 load was reduced to 800 MWe to investigate saltwater leakage into the main condenser.

6/4 Increased load to capacity (870 MWe) at 2300 after plugging one condenser tube.

6/7- At 1800 load was reduced to 800 MUe to investigate saltwater leakage into the main condenser. After plugging one condenser tube, resumed full load operation (855 MWe) at 2350.

6/8 Operated at reduced load (730 MWe) at 0800 while testing main turbine control valves. Resumed full load operation (365 MWe) at 2015.

6/12 At 2325 load was decreased to 780 MWe to replace #23B Travellina Screen.

6/13 Load was increased to capacity (870 fMe) at 0630 after repairs were completed.

6/15 At 0930 load was decreased to 580 MWe to repair #22 Steam Generator Feed Pump.

6/17 After completing repairs to #22 Steam Generator Feed Pump, load was increased to capacity (865 MWe) at 0930.

6/20 At 1600 load was reduced to 675 MWe to investigate saltwater leakage into the main condenser.

l 6/21 Increased load to capacity (860 MWe) at 0700 after plugging one condenser tube.

6/28 Operated at reduced load (730 MWe) at 2230 while testing main turbine control valves.

6/29 Resumed full load operation (875 MWe) at 0500.

6/30 At the end of this reporting period Unit 2 was operating-at

SuittARY OF UilIT 2 OPERATIfiG EXPERIEflCE - JUNE 1980 6/30 875 fNe with the reactor at 100% power.

l l

l l

l

SAFETY-RELATED MAIrlTEf!ANCE .

UflIT OfiE GROUP I&C MONTH JUNE YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION ,

  1. 11 Control Room Air 0-80-1055 Defective Temperature Air Conditioning Unit Replaced the Conditioning System 4/28/80 Transmitter would not cool the Control Temperature 0-TT-5350. Room. Transmitter 0-TT-5350.

Reactor Protective 0-80-1085 Defective Relay Receiving Intermittent Replaced the System / Channel "B" 4/22/80 XK-102 trip signals. relay XK-102.

Loss of Load Trip Unit Refueling Water Tank 0-80-1500 Defective 24VDC power Level indication pegged Replaced the 24 VDC Level Indication 5/2/80 supply for 1-LY-4142. 10w. power supply.

1-LY-4142

  1. 11 Steam Generator 0-79-2126 Position arm was ou,t The remote indication Adjusted the Bottom Blowdown Valve 7/16/80 of adjustment. for the valve showed position arm.

1-CV-4011 intermediate all of the time.

Spent Fuel Pool Level 0-80-1258 The level switch Receiving alarm condition Adusted the level Indication 4/17/80 0-LS-2002 was out when one did not exist. switch 0-LS-2002.

0-LS-2002 of adjustment. ,

t SAFETY-RELATED MAINTENANCE UNIT ONE GROUP I&C MONTH JUNE YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Liquid Waste Discharge 0-80-1757 The actuating ann for Valve position indication Adjusted the Valve 5/21/80 the valve position did not work properly. actuating arm for 0-CV-2202 indication switches the position switches ,

was out of adjustment. ,

9 Reactor Protective 0-79-2979 Defective dual The channel "A" lower Replaced the dual System 4/14/80 potentiometer with positive setpoint on the potentiometer and buffer amplifier module . axial shape index was the resistance Also a defective deteriorating over a temperature detector.

resistance temperature 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

detector 1-TE-122CA e

SAFETY-RELATED MAINTENA' ICE UNIT TWO GROUP I&C MONTH JUNE YEAR 1980 MALFlJNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Enginee-cd Safety 0-80-905 Broken Pin on the #23 Saltwater pump faii.1 Replaced the broken' Featt.ses Actuation 3/18/80 socket of Relay K63. to start during testing. pin in the socket System / Safety Injection of Relay K63.

Actuation Signal liodule .

B-8 -

Reactor Protective Systern 0-78-2885 Defective digital Peceiving erratic readings Replaced the Calibration and 10/19/78 vol tmeter. on channel "C" calibration digital voltmeter.

Indication Panel and indication panel.

Channel "C" Engineered Safety 0-80-657 Defective Signal The signal isolator Replaced the signal Features Actuation 3/3/80 Isolator would not calibrate. Isolator System Channel ZF 2-E/E-1023C 2-E/E-1023C Reactor Protective IC-80-2001 Defective digital The digital voltmeter Replaced the System Calibration 1/3/80 vol tmeter. would not change digital voltmeter.

and Indication Panel 'olarity properly at Channel "D" L t signal inputs.

l

SAFETY-RELATED MAINTENANCE UNIT TUO GROUP I&C MONTH JUNE YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Subcooled Margin 0-80-1242 Defective signal Subcooled Margin Monitor Replaced the signal Monitor /2-AE-21 4/16/80 converter 2-PY-102A operation was sporadic. converter 2-PY-102A.

for pressurizer pressure. ,

Reactor Protective IC-80-2043 Defective modules The Channel B negative Replaced modules System Axial Power 4/23/80 D4 & 05. limit indication was D4 & D5 in Channel Distribution Channel indicating low. "B" Axial Power "B" Distribution Drawer.

Refueling Water Tank 0-80-1968 Defective signal Received erroneous Replaced the signal Level Indication 6/3/80 isolator and power alarms and level isolator and power 2-LT-4142 supply. indications. supply.

a

. i. ,

_. . . _ _ . .. .- - . - . _ .S.*.

SAFETY-RELATED MAINTENE2 C

UtiIT 1 e

GROUP mchine Shop .-

6) i M3NTl! June YEAR' 1900' 2

IER OR MALFUNCTIOh SYSTEM OR COMPONENT MR NO. - DATE OUTAGE CAUSE RL'SULT CORHECTIVE ACTION 1-CV-5206 tio. 21 O-78-2723 Corrosion Irakage past seat Rglacedseat ,

Corponent Cooling S/29/79  !

H63t Exchanger Salt *

. .' i f mter Outlet Valve * '

ty . }'} .

. ~ *

  1. . - s.. .

a s;

l. . .

. l* ;-

1-CVC-105 M-78-317 Bent sttm Valve would only Replaced valv$ t '

1/12/79 partially cpen 12 Salt Water Purrp M-78-420 . . Corrosion to. bearings . Bearings overheated Replaced bearings 12/24/78 '

I due to 'flodling of '  !

  • pwp bay

~ .

  • e

. 0 0

l .x ... . . z. . - . -. . a .

SAFETX-SELATED MAINTENANCE .

o '

UNIT 2 .

I GROUP F4ichine Strp

- . . g s y, _

MONTI! June YEAR. 1980

  • LER OH IMLFUNCTION SYSTEM OR COMPGflENT MR NO. - DATE OUPAGE CAUSE RESULT CORRECTIVE ACTION 2-CV-4043 O-80-996 Rtptured bladder due Bladder would not feplacedbladde,r timin Steam Isolation 3/26/80 to cyclic fatigue hold te charge  !

valve Irw Pressure Ptsrv

  • s P Si.trge Stoppessor
  • J, , .~-[.f,.p

- 3

, ,]) ,' i \.

  • L - -

.. F, 21 Dnergency Diesel O-80-660 Cyclic fatigue of Diesel generator 1 -l'r Replaced goverpor Generator 3/10/80 governor fd1ed to cane to .. t rated @eed and '.

voltage vitthin ten

- (10) secorxh s.

'i ' i' ' : . .

  • r ' \ :

Rupt,ured bla,dder 21 Charging Ptap O-79--3070 Bladder would not Replaced bladder 2

Easurger .s 10/11/79 due to cyclic hold IJ ,cha s fatigue , .

o e

e #

0 te O

Retrieved from "https://kanterella.com/w/index.php?title=ML19321A029&oldid=2489723"