ML20062D565

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Monthly Oper Rept for Oct 1978
ML20062D565
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 11/15/1978
From: Merson S
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20062D561 List:
References
NUDOCS 7811240217
Download: ML20062D565 (18)
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Text

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OPERATING DATA REPORT DOCKET NO.60-117 DATE ll/l's/78

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CO31PLETED BY D. Merson TELEPHONE l-23h-52hD OPERATING STATUS b ***

1. Unit Name: Calvert cli f fa W .__.1...
2. Reporting Period: October. 1978
3. Licensed Thermal Power (Mht): 2700
4. Nameplate Rating (Gross MWe): 910
5. Design Electrical Ratingt (Net Mhe): %5
6. Maximum Dependable Capacity IGross MWel: 8h5
7. Maximum Dependable Capacity (Net MWe): 810
8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Sin'ce Last Report.Gi+e Reasons:

(Net MWe): um

9. Power Lesel To which Restricted.If N Any/A
10. Reasons For Restrictions.If Any:

This Month Yr..to.Date Cumulative

11. Hours in Reporting Period 7h5 7,296 30,$hl
12. Number Of Hours Reactor Was Critical 735 6.218.0 2h.921.6
13. Reactor Resene Shutdown Hours 10.0 48.7 496.6
14. Ilours Generator On.Line 731.h 5.0h6.3 2h.h18.0
15. Unit Resene Shutdown llours 0.0 n.n n_n
16. Gross Thermal Energy Generated (MWH) 1.8h0.419.0 12.089.121 R 58_CCR_nliA), .
17. Gross Electrical Energy Generated (MWH) 611.126_ _ _,. 1.996.278 19Ih 71 '_991
18. Net Electrical Energy Generated (MWH) 58h.819 1.801.714 18'<A95<Rn
19. Unit Senice Factor 98.2 ' 69.2 " 80.0
20. Unit Availability Factor 98.2 69.2 80.0
21. Unit Capacity Factor iUsing MDC Net) 96.9 6h.h 75,1
22. Unit Capacity FactorIUsing DER Net) 92.9 61 . 7 79 n
23. Unit Forced Outage Rate 1.8 10.1 6_A
24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date.and Duration of Eacht:

Calvert Cliffs No.1 is scheduled for a planned outage startine Anril lb.1979.

and will be 6 weeks in duration for Reneral insoection and refueline.

25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status 1 Prior to Commercial Operationi: Forecast Achieved INITIA L CRITICA LITY

- INITIA L ELECTRICITY COMMERCI AL OPERATION l

(Q/77)

OPER ATLNG DATA REPORT DOCKET NO. 50-318 DATE 11/1 </7A COMPLETED BY TELEPHONE S.~D'.hisb 301-2314-52 OPERATING STATUS Calvert Oliffs No. 2 Notes I. Unit Name:

2. Reporting Period October. 1978
3. Licenxd Thermal Power (Mht): 2700
4. Nameplate Rating (Gross MWei- 911
5. Design Electrical Ratmg(Net MWe): Sh5
6. Maximum Dependable Capacity IGross Mhen: AhC
7. Masimum Dependabic Capacity (Net MWe): 810
8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report.Give Reasons:

Net MWe): 374 net M.fa

9. Power LevelTo which Restricted.If
10. Reasons For Restrictions.lf Any: Der Any (forming cycle two escalation to Dower ohvsica _

testing This Month Yr. to Date Cumulative i1. Hours In Reporting Period 7h5 7296 13.896

12. Number Of Hours Reactor was Critical 77.0 cLgqq,9 11_ggh,1
13. Reactor Resene Shutdown Hours 0.0 ' 72.5 119.h
14. Hours Generator On Line 72.6 47h7.2 11.hph.1
15. Unit Resene Stutdown llours 0.0 0.0 0.0 I6. Gross Therman Energy Generated IMWH1 8h.h78 11.199.99h.9 27 hC9_1R7 n -
17. Gross Electrical Energy Generated (MWHI 26;65h_ ,,,

jf.3h5'.792 9 ',100',17h

18. Net Electrical Energy Generated (MWH) 16.901 h .19h .8h 8 8.AAA 9n9
19. Unit Senice Factrr 9.7 78.8 82.2-
20. Unit Availability Factor 9+7 78.8 82.2 '
21. Unit Capacity Factor iUsing MDC Neti 2.8 69.8 77.0 i
22. Unit Capacity bctor IUsing DER Net) 2.7 66.9 71.8 _

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23. Unit Forced Outage Rate 0.0 8.9 6.4
24. Shutdowns Scheduled Oser Nest 6 Months IType.Date and Duration of Eacht:

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

l 26. Units In Test Stati:sIPrior to Commercial Operationi: Forecast Achieved INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCIA L OPE R ATION (0/77)

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AVER AGE D AILY UNIT POhER LEVEL DOCKET NO. Sn 317 UNIT Enlvart oli ffa #1 DATE 11/lC/78 -

COMPLETED BY S. D. h rson TELEPHONE 3n' .9 th.49hn MONTH Octcha"- 1978 DAY AVERAGE D AILY POWER LEVEL DAY AVERAGE DAILY POhER LEVEL (MWe Net) (MWe Net) 811 37 808 2 815 18 795 3 810 39 807 4 806 20 793 5 802 21 771 6 795 22 838 7 758 25 833 g 831 24 791 9 *M6 25 71 10 518 26 795 I 5hh 27 777 12 76h 28 8hl 13 773 29 Ohl 14 788 3, 8h1 15 829 31 838 16 818 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.

(9/77) f l

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  • AVERA(A D AILY UNIT POhER LEVEL DOCKET NO. 50-318 UNIT Calvert Cliffs #2 DATE 11/16/78

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COMPLETED BY S. D. Merson TELEPHONE 101 -23h-42ho MONTil October,1978 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POhER LEVEL (MWe Net) 1MWe Net s 17 2 18 -

3 19 -

4 -

20 -

5 21

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6 22 7 D 8 24 -

9 25 -

l 10 - -

26 1I 27 -

12 28 -

13 29 268

, 14 30 357 I

15 31 383 16 INSTRUCTIONS On this format, list the average daily unit power lesel in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

19/77)

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9 DOCKET NO. 5^-31 ~7 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Calvert c11rr* No. 1 DATE 11/19/78 COMPLETED BY S D- *"= j REPORT MONTH n,+ h, 1978 TELEPHONE ini 9th _ gor n 3 1

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. - .y g 3 h h* Licensee 5 t, 4 Cause & Corrective No. Date h, 3g i 2s5 Event g? gU3 Attism to t- y 5 j ;f, g Report 8r 'a O g Prevent Recurrence d .

l 78-16 781010 F 13.6 A 3 LER-Ok? EB CKTBRK Forced outage due to 13KV circuit breaker #252-?lOh tripping due to unknown causes, resulting in the loss of control power to No. 12 Steam Generator Feed Purip. This caused a low-steam generator level i

cor.dition which resulted in a plant trip.

I 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram- Entry Sheets for Licensee C-Refueling 3 Aufomatic Scram- Event Report (LER) Fde INtlREG-D. Regulatory Restriction 4-Other (Explain) 01611 1: Operator Training & IJcense Examination F Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source 19/77) 11-01her (Explain)

DOCKET NO. 50 ~418 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Calvert Cliff = No. 2 DATE 11/15 /7A COMPLETED BY S. D. b rson REPORT MONTH OctoM e, 1978 TELEPHONE 301-23h-52ho e.

- E c j? 3- y $5 Licensce ,E't, {4 Cause & Correttive f

No. Date i 3g 4 2s5 Event p g*3 Attum to l

6-f: 5 gg Report 8 mO g Pievens Resurrence c5 78-18 780916 S 672.h C h N/A Scheduled outage for reactor general inspection, refueling and unit inspec-tion (continuation of scheduled outage from previous month).

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i l 2 3 4 F: Forced Reason: Method: Eshibit G -Insieuctions S: Scheduled A Equipment Failure (Explain) l-Manual for Preparation of Data B-Mainienance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Au somatic Scram. Event Report (LE R) File (NURLG-D Regulatory Restriction 4 Other (Explain) 0161)

E Operator Training & Ucense Examination F-Admmistrative -

5 G-Operational Error (Explain) Exhibit 1 Sann Source (9/77) Il-Other (E xplain)

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I Updated:

11/9/78 REFUELING INFCRMATION RECUEST

1. Name of Facility:

Calvert Cliffs Nuclear Power Plant, Unit No.1

2. Scheduled date for next Refueling Shutdown: -'

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April 14, 1979 n

3. Scheduled date for restart following refueling:

May 22, 1979 "

k. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Resumption of operation after refueling vill 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.

February 5, 1979

6. Important licensing copaiderations associated with refueling Reload fuel vill 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 i

(b) 228'

  • Spent Puel 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 Current Installed 840 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.

September, 198h

    • Information which has changed since last. monthly report.

i Updated:

11/9/78 REFLTLING INFORMATION REQLTST

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

2. Scheduled date for next Refueling Shutdown:

10/1/70** .

3. Scheduled date for restart following refueling:

11/8/79**

h. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Resumption of operation after refueling vill require changes to s Technical Specifications. The changes vill 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 I'

supporting information.

July la$, 1978

6. Important licensing considerations associated with refueling.

Reload fuel vill be similar to that reload fuel inserted into the Cycle 3 of Unit 1.**

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7. The numbe'r of fuel, assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 217 '

(b) 228'

' Spent Puel 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, t

1056 Licensed 728 Currently Installed Sh0 Addition is planned

9. The projected date of the last refueling that can be discharged to 1

the spent fuel pool assuming the present licensed capacity.

September, 198h

    • Information which has changed since list monthly report.

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SUMMARY

OF UNIT 1 OPERATING EXPERIENCE October 1978 10-1 At the beginning of this reporting period. Unit 1 was operating at 852 MWe. Reactor power was limited to 95% power by the Environ-

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mental Technical Specification (ETS) of 10*F limit on the main

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condenser circulating vater o T.

10-7 Recuced load to 671 MWe at 0605 to clean main condenser water boxes.

Full load operation (865 MWe) resumed at 1730. Reactor power was limited to 95% by the ETS limit of 10*F on main condenser circulating water J1 T.

10-9 Reduced load to 720 MWe at 0950 to investigate salt vater leakage into the main condenser.

10-10 Resumed full load operation (870 MWe) at 0330 after plugging one tube. At 1h29 21 13ky bus feeder breaker spuriously opened causing a loss of steam generator feed pump control power. The Unit tripped on low steam generator level at 1532.

10-11 The reactor was brought critical at 013h and the unit was paralleled at 0506. Load was increased to 851 MWe. Reactor Power was limited to 95% by the ETS 10*F limit on main condenser circulating water di T.

10-12 Reduced load to 705 MWe at 1505 to investigate salt water leakage into the main condenser.

10-13 Resumed full load operation (861 MWe) at 1730 after plugging one tube.

Reactor power was limited to 95% by the ETS 10*F limit on main con-denser circulating water 21 T. Reduced load to 699 MWe at 2200 to clear incora detectors alarms.

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1 10-14 Resumed full load operation (865 We) at 0815 after alarms cleared. I Reactor power was linited to 95% by the ETS 10'T limit on main circulating condenser water A T.

10-20 Reduced load to 700 We at 2115 to clean main condenser water boxes. ,

10-21 Resumed full load operation (868 We) at ik00. Reactor power was limited to 955 by the ETS 10*F limit on main condenser circulating water A T.

10-2h Reduced load to 666 We at 2145 to clean main condenser water boxes.

10-25 Full load operation (8h3 We) resumed at 1h00. Reactor power was limited to 925 by the ETS 10'F limit on main condenser circulating water A T.

10-26 Reduced load to 685 We at 2130 to clean main condenser water boxes.

10-27 Resumed full load operation (864 We) at 1226. Reactor power was limited to 95% by the ETS 10*F limit on main condenser circulating water A T.

10-31 At end of this reporting period Unit 1 was operating at 871 We with the reactor at 97% power, power being limited by the ETS 10'F limit on main condenser circulating water A T.

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4 SUIC4ARY OF UNIT 2 OPERATING FXPERIENCE 4

October 1978 10-1 At the beginning of this reporting period Unit 2 was shut down for its first scheduled refueling outage. r

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10-13 Completed refueling operations at 0927 10-16 Installed the reactor vessel head at 1020.

10-23 Beactor coolant system heatup completed at 1200.

j 10-25 Initial cycle two reactor criticality was achieved at 13h2. The reactor tripped on lov steam generator level at 2108.

10-26 The reactor was brought critical at 0220.

10-27 The reactor was shut down at 1925 to perform maintenance on several items.

10-28 The reactor was brought critical at 2000. The unit was paralleled at 2138. At 2228 CEA 01 dropped into the core and the turbine was tripped from 11% power to stabalize the transien6.

10-29 The unit was paralleled at 0110 EST and began increasing load to 50% power physics test plateau.

10-31 At the end of this reporting period Unit 2 was performing cycle two escalation to power physics testing. Unit 2 was operating at k12 MWe with the reactor at 50% power.

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.3AFETY-RELATED MAINTENANCE UNIT l GROUP _ Mechanical MONTH October YEAR 1978 MALFUNCTION I*

SYfrDi OR COMPONDIT ffR NO. - DATE CAUSM '

RESULT CORRECTIVE ACTION

  1. 19 H.P. Accumulator 0-78-1810 6/2/78 Replaceabit fittings Bladder didn't hold N2 Rebuilt accumulator
  1. 11 MSIV Package worn precharge

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SAFEfY-RELATED MAINTE WICE UNIT 1 GROUP ELECTRICAL MONTH October YEAR 1978 MunincTroa SYEPE2f OR CO!GONE'IT MR NO. - DATE C/USE R~EUT.T r CORRECTIVE ACTION 23 Charging Pump 0-78-3342 10/23/78 Defective charging 23 Charging pump Replaced charging motor on breaker would not start motor.

52-2404.

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  1. 11 MSIV High Press Pump 0-78-3250 10/17/78 Defective coil on #12 High press pump Replaced solenoid unloader Solenoid 'l-SV-9626 would not start valve coil and 1-SV-9626 control circuit fuse.

fuse blew.

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JAFETY-RELATED MAI?TIENANCE -

UNIT 1

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GROUP I&C MONTH October YEAR 1978 MALMJNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION ESFAS 11 Steam Gen- 0-78-3029 9/25/78 Defective voltage Voltage readings .2 Replaced voltage crator Pressure isolator volts higher than isolator Channel ZD 1-E/E-1013A other channels I

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SAFETY-RELATED MAINTENANCE -

ImIT 2 GROUP ELECTRICAL MONTH October YEAR 1978 fiALMINCTION

  • SYSPD4 OR COMPONEh"P MR NO. - DATE CAtISE RESULT CORRECTIVE ACTION 125 V.D.C. Distribution E-78-190 10-11-78 Defective under voltage Under voltage alam in Replaced under Panel DC-22-2012 Under relay Control Room voltage relay Voltage Relay 27/D22
  1. 21 Charging Pump 0-78-3312 10-21-78
  • Defective closing coil 21 Charging pump would Replaced closing on breaker 52-2115 not start. coil
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SAFETY-RELATED MAINTENAqCE UNIT 2 GROUP I&C MONTH October YEAR 1978 MALRINCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE R"oDLT CORRECTIVE ACTION Under Voltage Module 2-IC-78-155 Defective module Module wouldn't trip Replaced under for 4KV Bus #21 10/19/78 when test button was voltage module.

Chn. ZG pressed.

Pressurizer Vapor 0-78-3506 10/21/78 , Defective solenoid Valve would not open. Replaced solenoid Sample Valve 2-CV-5465 valve 2-SV-5465 valve Reactor Regulating , 0-77-4188 10/31/78 Defective RTDs Indication for T-hot Replaced both System Loop 21 T-Hot failed high, indication RTD's.

2-TE-111X for T-cold was oscilla-Loop 21T-Cold 2-TE-115 .

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CVCS Charging and 2-IC-78-144 Flow transmitter During PM-2-41-I-R-1 Made adjustment Letdown System 10/6/78 oscillator out of transmitter readings to oscillator

. 2-FT-202 Letdown adjustment. were out of tolerance circuit.

! Line Flow -

on low end of range.

- a.--- ,- . . . - , - - . - ----;, -m - - ~, . , - , . - - - - - - , - - - - , - - -,- -.

SAFErY-RELATED MAINTDiANCE -

UNIT 2 GROUP IAC MONTH October YEAR 1978 MALRINCTION SYSTDI OR COMPONENT MR NO. - DATE CAUSE RESIILT CORRECTIVE ACTICH R: actor Regulating 0-78-1201 4/15/78 Defective RTD Indication for T-cold Replaced RTD.

System Loop 22 T-Cold failed high.

2-TE-125 Radiation Monitoring 0-77-4147 10/27/78 Defective Geiger-Mueller Periodic alarms Replaced Geiger- l System 2-RI-53160 ' tube and driver printed Mueller tube and circuit assembly (A2) driver printed circuit assembly b

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SAFErY-RELATED MAINTDIANCE .

UNIT 2 Mechanical CROUP M0FfH October YEAR 1978 MALFUNCTION SYCPFM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION i

  1. 22 Switchgenr Gear 0-77-4618 6/15/78 Malfunction of oil Compressor did not stop Repaired oil Room A/C Unit Compres- pressure regulator and on low oil pressure pressure regulator sor oil pressure switch. signal, and low oil pressure switch
  1. 21 Aux. Feed Pump 2M-77-2182 10/1/78
  • Pin hole leak in cooler Cooling water leakage Replaced cooler Governor Unit 2 Emergency Air , 2-IC-78-159 10/20/78 Worn teflon seals Excessive leakage Replaced valve Lock Equalizing Ball Valve (Outside) 2-SW-197 30" Pratt M-77-2381 10/4/78 Broken lever and Unable to stroke valve Rebuilt operator Butterfly valve eccentric bearing (MDT-4 operator) 0-78-2062 6/25/78 Weld failure Makeup leakage Repaired weld

) #22 Charging Suction HeaderPump imediately down stream ~

of 2-CVC-501

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