ML19305B306

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Monthly Operating Repts for Feb 1980
ML19305B306
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 03/13/1980
From: Merson S
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19305B304 List:
References
NUDOCS 8003190491
Download: ML19305B306 (2)
v • d • e


Text

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O OPERATING DATA REPORT DOCKET NO. 502317 DATE 3/13/80 COMPLETED BY S. D.

Merson i

TELEPHONE 101 ?14 5240 l

OPERATING STATUS Notes

1. Unit Name:

Nv-C14#fa No-1 Februarv, 1980

2. Reporting Period:

2700

3. Licensed Thermal Power (MWt):

918

4. Nameplate Rating (Gross MWe):

845

5. Design Electrical Rating (Net MWe):

845

6. Maximum Dependable Capacity (Gross MWe):

810

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

l l

9. Power Level To Which Restricted.If Any (Net MWe): 7 0 MW, turbine blade oroblems.

No. 1 is reduced to 790 MW due to turbine blade problems.

10. Reasons For Restrictions.If Any:

nn ~1/25/80. No. 1 vas recorted on, nianned outace to nerform TMI modifications re:cuired by NRC.

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The Plant was reported in service on 2/12/80, good for 790 "U.

This Month Yr..to.Date Cumulative 696.0 1,440.0 42,205.0

11. Hours in Reporting Period 451.8 1,052.2 33,491.8
12. Number Of Hours Reactor Was Critical 0.0 0.0 1,060.5
13. Reactor Reserve Shutdown Hours 428.0 1,028.0 32,730.0
14. Hours Generator On.Line
15. Unit Reserve Shutdown flours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 781,960.8 1,711.687.2 77,048,676.0 244,542 516,670 25,329,200
17. Gross Electrical Energy Generated (MWH,
18. Net Electrical Energy Generated (MWH) 227,541 478,003 24,127,209 61.5 71.4 77.6
19. Unit Service Factor
20. Unit Availability Factor 61.5 11.4; 77.6 40.4 41.0 70.6
21. Unit Capacity Factor IUsing MDC Net) 38.7 39.3 67.7
22. Unit Capacity Factor (Using DER Net)
23. Unis Forced Outage Rate 0.0 0.0 8.8
24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each): __

l

25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units In Test Status (Prior o Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (4/77) 8003190 (C7

OPERATING DATA REPORT DOCKET NO. 50-118 DATE 1/11/80 COMPLETED BY <- D. Merson TELEPHONE 1m -214-5240 OPERATING STATUS Calvert Cliffs No. 2 Notes j

.. Unit Name:

February, 1980

2. Reporting Period:

2,700

3. Licensed Thermal Power (MWt):

911

4. Nameplate Rating (Gross MWe):

845

5. Desagn Electrical Rating (Net MWe):

860

6. Maximum Dependable Capacity (Gross MWe):
7. Maximum Dependable Capacity (Net MWe):

825

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,if Any:

This Month Yr. to Date Cumulative 696.0 1,440.0 25,560.0

11. Hours in Reporting Period
12. Number Of Hours Reactor Was Critical 696.0 1,220.9 21,165.8 0.0 0.0 413.1
13. Reactor Reserve Shutdown Hours
14. Hours Generator On Line 696.0 1,212.7

..,20,821.2

15. Unit Reserve Shutdown flours 0.0 0.0 0.0
16. Gross Thermal Energy Generated IMWH) 1,772,467.2 3,129,643.2 51,373,875.0
17. Gross Electrical Energy Centrated (MWH 591,761 1,047,947 17.053,170
18. Net Electrical Energy Generated (MWH) 568,445 1,001,537 16,258,557
19. Unit Service Factor 100.0 84.2 81.5
20. Unit Availability Factor 100.0 84.2 81.5 1
21. Unit Capacity Factor (Using MDC Net) 40.0 84.3 78.4 96.7 82.3 75.3
22. Unit Capacity Factor IUsing DER Net) 0.0 0.0 0.0
23. Unit Forced Outage Rate
24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Each):
25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved i

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

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AVERAGE DAILY UNIT POWER LEVEL 50-317 DOCKET NO.

Calvert Cliff.: #1 WIT DATE 3/13/80 i

S. D. Merson j

COMPLETED 8Y TELEPHONE

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February, 1980 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 380 i

17 386 1

2..__.

13 540 3

39 555 4

20 554 3

73 564 6

22 685 7

23 693 8

- 24 695 9

25 696

~

10 26 697 11 27 85 12 28 13 376 858 29 0

14 30 383 15 3i 16 380 INSTRUCTIONS On this format, list the average daily unit power level in MWe Net for each day in the reporting month'. Compute to the nearest whole megawatt.

i (9/77)

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j AVERAGE DAILY UNIT POWER LEVEL 50-318 DOCKET NO.

UNIT Calvere Cliffs #2 DATE 3/13/80 4.

S. D. Merson COMPLETED BY t

301-234-5240 TELEPHONE MONTH Februarv. 1480 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe. Net) 710 778 g

g7 829 757 7

g 8'4 763 3

19 862 0

4 20 714 5

AM gg 861-760 6

22 786 812 7

844 8

24 797 9

857 25 850 10 812 26 832 856 27 799

.I3 12 846 28 854 13 785 29 700 859 14 30 860 15 3,

836 I6 INSTRUCTIONS On this format, list the average daily unit power level in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

t UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-317 UNIT NAME Calvert cliffs jft DATE 8/13/MU S. D. Merson COMPLETED BY REPORT MONTH February, 1980 301-214-5240 TELEPHONE w.

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7sg 1.icensee E,

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Cause & Corrective

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Event f,?

Q Action to g

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fge y Di g Report a mO p, event Recurrence O-E g

6 80-01 800125 5

268.0 D

4 ZZ ZZZZZZ To perform THI modifications as required by NRC.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) l-Manual for Preparation of Data i

B Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG-

- D-Regult. tory Restriction 4-Con t i nua tion 0161)

E-Operator Training & Ucense Examination 5-Load reduction F Administrative 5

9-Other G-Operational Error (Explain)

Exhibit 1 - Same Source (9/77)

Il Other (Explain)

l DOCKET NO.

W j

UNIT SHUIDOWNS AND POWER REDUCTIONS UNIT NAME calvert c1iffs #2 DATE 1/11/M COMPLETED BY S-D. Merson

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REPORT MONTH Februn rv.

1980 TELEPHONE 301-214-5240 l

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2 c *g Licensee g*

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Cause & Corrective

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5 j ac Event RT gl Action to g'

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  • mO Prevent Recurrence l

o-ac C5 No Outages or Reductions.

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1 2

3 4

F: Forced Reason:

Method:

Exhibit G Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Pseparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling 3 Ausomatic Scram.

Event Repor (LERn File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination

)

F Administrative 5

G-Operational Estor (Explain)

Exhibit 1 -Same Source i

(9/77) llother (Explain)

3/7/80 REFUELING INFORMATION REQUEST 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 18, 1981 4.

Will refueling or resumption of operation thereafter require a technical specification change or other licensed amendment?

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

5.

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

November 20, 1980 6.

Important licensing considerations associated with refueling.

None, reload fuel will be identical 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 Spent Fuel Pools are common to Units 1 and 2.

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 planned, in number of fuel assemblies.

1056 Licensed 728 Currently Installed 704 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 report.

3/7/80 REFUELING INFORMATION REQUEST 1.

Name of Facility:.Calvert Cliffs Nuclear Power Plant, Unit No.1 2.

Scheduled date for next Refueling Shutdown:

October 17, 19C0*

3.

Scheduled date for restart following refueling:

December 10, 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.

September 11, 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 Spent Fuel Pools are common to Units 1 and 2.

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 704 Licensed Addition is Planned.*

9.

The projected date of the last reufeling that can be discharged to the Spent Fuel Pool assuming the prisent licensed capacity.

October, 1983.

  • Information has changed since last report.

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE-FEBRUARY 1980 2/l At the beginning of this reporting period Unit I was shutdown for installation of the NRC required plant modifications pursuant to NUREG 0578, 2/7 Completed filling the reactor coolant system at 2325.

2/11 Completed reactor coolant system heat-up at 0325.

The reactor was brought critical at 0412.

2/12 At 0358 the unit was paralleled.

2/13 Increased load to 410 MWe (50% power) at 0945.

Maintained this power to gather and analyze physics and core ap data to verify that the power distribution anomaly had been rectified.

2/19 At 0600 load was increased to 585 MWe (70% power) for further testing and analysis.

/23 Load was increased to 730 MWe (85% power) at 0445 for further testing and analysis.

2/29 At the end of this reporting period Unit 1 was operating at 730 MWe with the reactor at 85% power, while conducting core physics measurements to verify that the power distribution anomaly had been rectified.

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SUMMARY

OF UllIT 2 OPERATIflG EXPERIEllCE-FEBRUARY 1980 2/1 At the beginning of this reporting period Unit 2 was operating at 895 MWe with the reactor at 100% power.

At 0005 control element assembly (CEA) 32 dropped into the core. Reactor power was immediately reduced to less than 70% in accordance with the Technical Specifications. CEA 32 was withdrawn back to its group at 0100. Began increasing power and at 1000 load was limited to 815 MWe to investigate salt water leakage into the main condenser.

2/2 After plugging one condenser tube load was increased to 895 MWe at 1100.

2/3 At 0030 load was reduced to 805 MWe for main turbine control valve testing. Resumed full load operation (900 MWe) at 0400,-

2/6 Started to decrease load to 740 fNe at 2220 to clean condenser water boxes.

2/7 At 0700 increased load to capacity (905 FMe) and at 2200 load was reduced to 805 MWe to investigate salt water leakage into the main condenser.

2/8 Resumed full load operation (905 MWe) at 0600 after plugging one condenser tube, m

2/10 Decreased load to 770 MWe to clean condenser water boxes.

Resumed full load operation (895 MWe) at 1230.

2/13 Reduced load to 785 MWe at 0001 to clean condenser water boxes. Started increasing power and at 1300 reduced load at 810 MWe to investigate salt water

SUPNARY OF UNIT 2 OPERATING EXPERIENCE-FEBRUARY 1980 2/13 leakage into the main condenser.

Increased load to capacity (900 lMe) at 1000 after indications of salt water leakage into the main condenser disappeared.

2/16 At 2200 load was reduced to 790 lMe for cleaning of condenser water boxes. Started increasing power and at 1700 load was reduced to 790 MWe to investigate salt water leakage into the main condenser.

2/23 Started increasing load to capacity and at 0215 reduced load to 745 IMe to clean condenser water boxes.

Resumed full load operation (900 FMe) at 1120.

~

2/24 At 0935 control element assembly (CEA) 31 dropped into the core. Reactor power was immediately reduced to 70% in accordance with the Technical Specifications.

CEA 31 was withdrawn back to its group at 1036.

Load was increased to capacity (900 FMe) at 2350, 2/26 Reduced load to 810 MWe at 1200 to investigate salt water leakage into the main condenser. After indications of salt water leakage disappeared load was increased to capacity (900 MWe) at 0500. At 0900 load was reduced to 810 Sie to investigate salt water leakage into the main condenser.

2/27 At 1303 control element assembly (CEA) 44 dropped into the core.

Reactor power was imediately reduced to less than 70% in accordance with the Technical Specifications. CEA 44 was withdrawn back to its group at 1422.

2/28 Load was increased to capacity (90014!e) at 0300.

SumARY OF UNIT 2 OPERATING EXPERIENCE-FEBRUARY 1980 2/29 At the end of this reporting period Unit 2 was operating at 900 We with the reactor at 100%

power.

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SAFETY-RELATED MAINTENANCE UNIT TWO GROUP MECil. MAINT.

MONTH FEBRUARY YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Main. Steam Isolation 0-79-2362 12/20/79 Solenoid valve for Hain steam isolation Solenoid valve was Valve 2-CV-4048 blocking valve would valve would not partial replaced and main not open.

stroke while performing steam isolation STP-0-47-2 valve tested. Test satisfactory.

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GROUP I&c MONTH March YEAR 1980 i

MALFUNCTION SYSTEM OR COMPONENT MR N0. - DATE CAUSE RESULT CORRECTIVE ACTION

  1. 11 Emergency Diesel 0-79-1855 Controller was out, Controller would not Realigned the Generator / Service 8/23/79 of alignment operate properly which controller Water Controller would result in either 1-PDIC-1587 i

too high pressure or i

too low pressure Engineered Safety 0-79-4855 The Bistable meter was Greater than a.1 volt Adjusted Bistable Features Actuation 1/2/80 out of adjustment difference between meter System / Containment channels Pressure, Channel ZD for Containment Isolation Signal Chemical and Volume 0-79-2954 Position switch for The valve would indicate Adjusted the Control System 12/5/79 closed position in-intermediate when it position switch 1-CV-210X dication out of was actually shut.

adjustment Gas Analyzing System /

0-79-4820 Open position switch The sample valve would Adjusted tha 1-CV-5464 Reactor Coolan t.1/2/80 Hot Leg Sample Isolatia l ~

was cut of adjustment not indicate fully open position switch j

Valve i

SAFETY-RELATED MAINTENANCE UNIT I

GROUP I& C MONTH March YEAR 1980 l

MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

  1. 11 Emergency Diesel 0-78-1091 Defective valve Valve would not shut Replaced the valve Generator / Service Water 8-3-79 positioner fully pos i tione.-

Control Valve 1-CV-1587 Service Water System /

0-79-2311 Malfunction in Alarm Low Level Alarm failed Changed the resistor

  1. 12 Head Tank Level 9-8-79 Circuit to reset, with the level value in the low in spec.

alarm circuit, as per the manufacturer's recommendation Salt Water System /

0-79-4C16 Valve operator regulator The valve would not fully Adjusted the regulatc r 1-CV-5153 12/.12/79 output pressure was too close pressure to the low proper pressure Service Water System /

0-79-4641 Excessive amount of Caused switch to stick Replaced the positior 1-CV-5214 12/14/79 pai.nt on position and give a false indi-switch switch cation 4

SAFETY-RELATED MAINTENANCE UNIT II GROUP I&C MONTH March YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Engineer d Safety 0-79-4390 The signal isolator Greater than.1 volt Adjusted the e

Features Actuation 11/29/79 2-E/E-10130 was out deviation between signal isolator System / Steam Generator of adjustm6nt channels Isolator Channel ZG for #21 Steam Generator i

Steam Generator IC-79-2169 Defective transmitter Erroneous Level Replaced Trans-Level Indication 12/4/79 Indication mitter Transmitter 2-LT-ll 238 Service Water Heat IC-79-2121 Fittings on the air Air leaks Reolaced air line Exchanger / Salt Water 11/9/79 line to the valve to the valve Outlet valve operator were damaged operator 2-CV-5155 Radiation Monitoring IC-79-2101 Defective + 15 volt Readings out of tolerance Replaced the System /2-RI-5316D 10/16/79 power suppTy during testing power supply Containment Area Monitor

SAFETY-RELATED MAINTENANCE UNIT II GROUP I5C MONTH March YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

  1. 21 Emergency Diesel 0-79-4183 Unknown Damaged Instrument Replaced the Generator / Crankcase 12/11/79 Lines inr.trument Lines Pressure Instrument Lines Engineer d Safety fea-0-79-4476 Defective Signal Sensor channel failed Replaced the e

tures Actuation System /

'12/3/79 Isolator Low Defective Signal Steam Generator Iso-2-E/E-1013D Isolator lation Signal Channel ZG for #21 Steam Generator Reactor Protection

, 10-79-2165' Dirty Drauer Rollers Intemittent grounds Cleaned rollers System 11/28/79 on various RPS channels and slides for drawers on Channels A, B, C, & D Engineered Safety 0-79-2385 Module meter was out Greater than.1 volt Adjusted the module Features Actuation 8/8/79 of adjustment deviation between meter channels j

System / Steam Generator Isolation Signal, Channel ZD meter

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