ML19270H223

Monthly Operating Repts for May 1979

ML19270H223
Person / Time
Site:	Calvert Cliffs
Issue date:	06/15/1979
From:	Merson S BALTIMORE GAS & ELECTRIC CO.
To:
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ML19270H222	List: ML19270H221 ML19270H223
References
NUDOCS 7906250263
Download: ML19270H223 (13)

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{{#Wiki_filter:. . OPERATING DATA REPORT DOCKET NO. 50 ~317 DATE 6/15/79 COMPLETED BY s. D. Merson TELEPHONE 101-734-5240 OPERATING STATUS Notes

1. Unit Name: Calvert Cliffs No. 1

2. Reporting Period: Fw- 1979 2700-

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe): 918

5. Design Electrical Rating (Net MWe): 845

6. Maximum Dependable Capacity (Gross MWe): 845 810

7. Maximum Dependable Capacity (Net MWe):

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): None

10. Reasons For Restrictions.If Any:  !!/A This Month Yr..to-Date Cumulative

11. Hours In Reporting Period 744 3,623 35,628

12. Number Of Hours Reactor Was Critical 0.0 2,225.0 28,313.6

13. Reactor Reserve Shutdowa Hours 0.0 122.7 1,016.3

14. Hours Generator On Line n.o _ 2,196.8 27,741.8

15. Unit Reserve Shutdown flours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 0.0 5,562.437.2 66,832,641.6 .

17. Gross Electrical Energy Generated (MWH) 0 ._. 1,818.416 22,204,751

18. Net Electrical Energy Generated (MWH) 0 1.735.525 21.290.513

19. Unit Service Factor 0.0 60.6 77.9_

20. Unit Availability Factor 0.0 60.6 77.9

21. Unit Capacity Factor (Using MDC Neti 0.0 59.1 73.4

22. Unit Capacity Factor iUsing DER Net) 0.0 56.7 70.4

23. Unit Forced Outage Rate 0.0 16.8 8.5

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each t:

25. If Shut Down At End Of Report Period. Estimated Date of Startup: June 25,1979

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION '

2238 222 (9/77) 7906250}f]4

OPERATING DATA REPORT DOCKET NO. 50-118 DATE 6/15/79 COMPLETED BY S. D. Merson TELEPHONE 101 714 'i240 OPERATING STATUS Ca bert Cl W s No. 2 Notes

1. Unit Name: .

2. Reporting Period: May, 1979

3. Licensed Thermal Power (MWt):

2700

4. Nameplate Rating (Gross MWe): 911

5. Design Electrical Rating (Net MWe).845

6. Maximem Dependable Capac:ty (Gross MWe): 969

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.lf Any (Net MWe): None

10. Reasons For Restrictions,1f Any: N/A "Ihis Month Yr. to.Date Cumulative

11. Hours In Reporting Period 744 3,623 18,983

12. Number Of Hours Reactor Was Critical 723.4 3,400.5 16,393.0

13. Reactor Reserve Shutdown Hours 20.6 20.6 240.0

14. Hours Generator t .i-Line 705.4 3,331.3 16,143.1

15. Unit Reserve Shutdown ilours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1,852,308.0 8,597,440.8 39,481,457.4 .

17. Gross Electrical Energy Generated (MWH) 608,692 2,890,700 1>,144,ee4

18. Net Electrical Energy Generated (MWH) 532,127' __ ,, 2,766,053 12,534,082

19. Unit Service Factor 94.8 91.9 8 5_. 0..

20. Unit Availability Factor 94.8 91.9 85.0

21. Unit Capacity Factor IUsing MDC Net) 06.6 94.3 81.5

22. Unit Capacity FactoriUsing DER Net) 92.6 90.4 78.1

23. Unit Forced Outage Rate 5.2 2.9 5.3

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

Calvert Cliffs No. 2 is scheduled for a olanned outage starting October 6, 1979, and will be six weeks in duration for general inspection and refueling.

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

26. Units In Test Status IPrior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 2238 223 en

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. J0-117 UNIT Calvert Cliffs #1 DATE 6/15/79 COMPLETED BY S. D. Merson TELEPHONE 301-234-5240 _ MONT11 Mny 1970 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) (Mwe. Net) I 17 - 2 - 18 3 19 4 20 5 21 6 22 1 y - 8 24 9 25 -

                                    -                                                           -              ~

10 26 l1 27 12 28 13 29 14 30 15 33 16 . 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 megawatt. 2238 224 om,

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-318 UNIT calvert Cliffs #2 DATE 6/15/79 COMPLETED BY S. D.-Merson TELEPHONE 301-234-5240 MONTil "w- 1070 DAY AYERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (Mwe. Net) 3 856 g7 038 2 857 gg 841 858 842 3 ,9 4 860 795 20 854 841 5 839 840 6 22 7 544 482 23 716 676 8 , 9 847 25 835 10 848 838 26 gg 845 73 27 843 720 12 23 33 842 835 29 842 834 34 30 844 833 15 33 839 INSTRUCTIONS On this format, list the averag,e daily unit power level in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt. 2238 225

DOCKET NO. 50-317 UNITSHUTDOWNS AND POWER REDUCT10NS UNIT NAME Calvert Cliffs Noa 1 DATE D/15/74 COMPLETED ay S. D. Merson REPORTMONTil May, 1979 TELEPilONE 101-234-5240

                                                      -      :                            g
                                     .$ E      3g     yY           Licensee     Eg        g4                Cause & Corrective No.          Date

{ 3g g$ 6 cE

                                                      ,3 g a}:

3 gg c Event Report a g mO

a. "

Action to Prevent Recurrence

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79-3 790421 S 744.0 C 1 N/A RC FUELXX Scheduled outage for reactor inspec-tion and refueling and unit inspec-tion. N N . U CD 1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions N S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data N B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee & C-Refueling 3-Automatic Scram. Event itspwt (LER) File (NUREG-D-Regulatory Restriction 4-O her(Explain) 0161) E-Operator Training & Ucense Examination F. Administrative 5 G Operational Error (Explain) Exhibit I - Sanw Source (9/77) Ilosher (Explain)

a DOCKET NO. 50-318 UNITSil'ITDOWNS AND POWER REDUCRONS UNIT NAME Calvert Cliffs No. 2 DATE 6/15/79 COMPLETED By S.D. Herson REPORT F'.ONDI May. 1979 TELEPIIONE 301-234-5240 "i - No.

                                     .[E       3       .h   Yk      Licensee       Eg         ,,               Cause & Corrective Date k     3g          i     ,g g $         Event       ~?

g g3 Action to H $ ,, 5 j di g Report a mO g U Prevent Recurrence 6 79-7 790507 F 9.4 A 3 N/A EC CKTBIW Forced outage due to a blown fuse on DC power to 21 inverter which caused actuation of the "ESFAS" turbine undervoltage relay. 79-8 790523 F 10.6 A 1 N/A EC TRANSF Forced outage taken in order'to reapir an oil leak on unit trans-former U-22000-22. 79-9 790527 F 18.6 A 1 N/A EG TRANSF To repair an oil leak on unit transformer U-22000-22 N N U oc> I 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions N S: Scheduled A-Equipment Failure (Explain) I-Manual for Preparation of Data g B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee q C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161) E-Operator Training & Ucense Examination F Administrative 5 G. Operational Error (Explain) Exhibit I - Same Source (9/77) 11-01her (Explain)

6/12/79 REFUELING INFORMATION REQUEST

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

~

2. Scheduled date for next Refueling Shutdown: April 19, 1980

3. Scheduled date for restart following refueling: May 29, 1980

4. Will refueling or resumption of operation thereafter require a technical speci-fication change or other license amendment?

Resumption of operation after refueling will require changes to Technical Speci-fications. 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.

February 22, 1979

6. Important licensing considerations associated with refueling.

Reload fuel will be similar to that reload fuel inserted into the previous cycle. Selected fuel assemblies will be modified by installation of sleeves in the Guide Tubes.

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

(a) 217 (b) 300 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.

l056 Licensed 728 Currently Installed 650 Addition is Planned

9. The projected date of the last refueling that can be discharged to the spent fuel pcol assuming the present licensed capacity.

October, 1983

                                                           ~

2238 228

6/12/79 REFUELING INFORMATION REQUEST

1. Name of Facility: Calvert Cliffs Nuclear Power Plant, Unit 2

2. Scheduled date for next Refueling Shutdown: October 6, 1979

3. Scheduled date for restart following refueling: November 14, 1979

4. Will refueling or resumption of operation thereafter require a technical speci-fication change or other license amendment?

Resumption of operation after refueling will require changes to Technical Speci-fications. 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 infonnation.

August 15, 1979 **

6. Important licensing considerations associated with 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) 300 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 650 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 monthly report.

2238 229

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE May 1979 5/1 At the beginning of this reporting period, Unit I was shut down for its scheduled third refueling outage. 5/21 At 0750, completed refueling the reactor. 5/29 At 2200, the reactor vessel head was installed. 5/31 At the end of this reporting period, Unit I remained shut down for its scheduled third refueling outage. 2238 230

SUMMARY

OF UNIT 2 OPERATING EXPERIENCE May 1979 5/1 At the beginning of this reporting period, Unit 2 was operating at 900 We with the reactor at 100% power. 5/5 Load was reduced to 765 We at 2330 for main turbine control valve testing. 5/6 Full load operation (895 We) resumed at 0530 after completion of control valve testing. 5/7 The main turbine was automatically tripped at 1530 due to a blown fuse on DC power to 21 inverter, which caused an actuation of the engineered safety features Actuation System Turbine UV relay. The reactor tripped on loss of load. The reactor was brought critical at 2510. 5/8 The Unit was paralleled at 0055. Full load operation (883 We) resumed at 2330. 5/20 Load was decreased to 767 We at 0015 for main turbine control valve tes ting. Full load operation (870 We) resumed at 0600. At 1144 control element assembly (CEA) 36 dropped into the core.

 ,      Reactor power was innediately reduced to less than 70% in accordance with the Technical Specifications. CEA 36 was withdrawn back to its group at 1230. Full load operation (870 We) resumed at 1830.

5/23 Began reducing load at 1150 to take the main turbine off line to re-pair an oil leak on Unit transformer U-22,000 - 22. The Unit was taken off line at 1545. The reactor remained critical. 5/24 The Unit was paralleled at 0216. Full load operation (860 We) re-sumed at 1230. 5/27 Began reducing load at 0025 to take the main turbine off line to repair an oil leak on Unit transformer U-22,000- 22. The Unit was taken off line at 0424. The reactor tripped at 0434 due to low steam generator levels. The reactor was brought critical at 1729 and the Unit was paralleled at 2258. 5/28 Full load operation (870 We) resumed at 1600. 5/31 At the end of this reporting period, Unit 2 was operating at 870 We with the reactor at 100% power. 2238 231

SAFETY-RELATED MAINTENANCE UNIT I GROUP I&C MONTH MAY YEAR 1979 , MALFUNCTION SYfirEM OR COMPONENT MR NO. - DATE CAUSE RESILT CORRECTIVE ACTIOF , Wide Range Nuclear IC-19-011 1/10/79 Defective proportional Low so_urce counts Replaced detector Instrumentation counter Channel "D" Wide Range Nuclear IC-79-010 1/10/79 Defective proportional Low source counts - Replaced detector Instrumentation counter Channel "B" e N tra CD N tra N

SAFETY-RELATED MAINTEN/11CE UNIT I GBOUP MAINTENANCE MONTH MAY YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

     #11 Salt Water Pump   M-78-407   7/11/78   Badly worn shaft sleeve,    Excessive gland leakoff. Reconditioned stuff-shaft, and bearings.        No adjustment of gland   ing box, replaced    '

Stuffing box covered possible. shaft, shaft sleeve, with scale and deterio- and bearings. Re-rated paint. packed pump. 1-RV-325 M-79-156 1/31/79 Scratched disc seating Valve leaked by seat Replaced disc

     #12 Charging Pump                          surface                                              assembly Discharge Relief Valve
   ~ 1-M0V-509             M-79-280   3/15/79   Natural end of life -      Motor operator would      Rebuilt motor Boric Acid Storage                         cyclic fatique of parts. not cycle                operator.

[[j Tanks to Charging Pumps (,, CD N Lea LeJ

SAFETY-RELATED MAINTENANCE UNIT II GROUP IEC MONTH MAY YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Reactor Protective 0-79-356 1/28/79 Defective flow trans- Reading out of tolerance

                                                                                    ~

Replaced flow System / Reactor Coolant mitter instrument. transmitter and Total Flow' Channel "D" 2-PDT-lllD repacked instrument caused by leaking isolation valve isolation valve

    #24 Containment Air      0-79-884   3/11/79   Defective flow trans-      Indicator pegged low        Replaced flow Cooler / Service Water                       mitter                                                 transmi.tter Flow Transmitter 1-FI-1592 e

N U CD N u k

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