ML19254D301

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Monthly Operating Rept for Sept 1979
ML19254D301
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 10/15/1979
From: Merson S
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19254D300 List:
References
NUDOCS 7910230567
Download: ML19254D301 (16)
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OPERATLNG DATA REPORT DOCKET NO. 50-317 DATE tr/15/79 COSIPLETED BY 9 n. Wrson TELEPHONE 3nt-? h-5240 OPERATING STATUS Notes

1. Unit Name: C,1 vert cliffs vo. I Sectember, 1979
2. Reporting Period:
3. Licensed Thermal Power (MWt): '7Fn
4. Namep! ate Rating (Gross alwe): 01A
5. Design Electri.al Rating (Net MWe): 865
6. Maximum Dependable Capacity (Gross 51We): "65
7. Maximum Dependable Capacity (Net 31We): 810
8. If Changes Occur in Capacity Ratings (!! ems Number 3 Through 7) Since Last Report. Gise Reasons:
9. Power Level To Which Restricted. If Any (Net MWe): 7 0 0 '"4 a
10. Reasons For Restrictions.lf Any: 91ade nroblens in the hich-oressure turbine.

This Month Yr..to.Date Cumulative

11. Hours In Reporting Period 720 6,551 18,556
12. Number Of Hours Reactor Was Critical 713.5 4,154.3 ~

30,247.4

13. Reactor Resene Shutdown Hours 6.5 144.6 1,Cc3.2
14. Hours Generator On.Line 710.4 3,980.6 2",523.6
15. Unit Resene Shutdown flours 0.0 0.0 C.v
16. Gross Thermal Energy Generated (MWH) 1,352,363.2 u,u34,507.o 71,204,712.v .
17. Gross Electrical Energy Generated (SIWH) ~ 7 5. 0 5L _, 3.I;2.'.03 23,53s,323
18. Net Electrical Energy Generated (Mb H) 549,747 2,uo6,352 22,451.340
19. Unit Senice Factor "8.7 60.S 70.e
20. Unit Availability Factor "S.7 60.3 76.6
21. Unit Capacity Factor (Using MDC Net "4.1 56.5 71.9
22. Unit Capacity Factor IUsing DER Net) "O.2 54.1 63.9
23. Unit Forced Outage Rate 1.3 10.8 9.5
24. Shutdowns Scheduled Over Next 6 5tonths(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 Operationi: Forecast Achieved INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCI AL OPER ATION

/ 346 (9/77) 7 D102 3 0 5 f 7

OPERATING DATA REPORT DOCKET NO.50-11F

'"/';/7' DATE COMPLETED BY c - D. 'derson TELEPHONE ' '" " 4 - 5 2 40 OPERATING STATUS Calvert Cliffs No. 2 Notes

1. Unit Name:

Se tember, 1979

2. Reporting Period:
3. Licensed Thermal Power (MWt): '7en
4. Nameplate Rating (Gross MWet 411
5. Design Electrical Rating (Net MWe): 345
6. Maximum Dependable Capacity (Gross MWet 34i
7. Maximum Dependable Capacity (Net MWe): 810
8. If Changss Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gi e Reasons:
9. Power Level To which Restricted. If Any (Net MWe):
10. Reasons For Restrictions. lf Any:

This Month Yr..to-Da te Cumulative

11. Hours In Reporting Period 720 6,551 21,911
12. Number Of Hours Reactor Was Critical 570.4 6,024.6 10,017.1
13. Reactor Resene Shutdown flours 14.8 IS9.7 409.1
14. Hours Generator On Line 562.5 5,90".1 _c.720.9
15. Unit Resene Shutdown flours 0.0 o,o a,o
16. Gross Thermal Energy Generated (MWH) 1.400,l"9.4 15.225,235.2 4e,104,251.F ,
17. Gross Electrical Energy Generated tMWHi 458,e08 _ 5,e40,206 15.2% , h
18. Net Electrical Energy Generated (MWH) '36,087

' 4.315,438 IL,5F3,517

19. Unit Service Factor 7f .1 "e.2 d5.c
20. Unit Avadability Factor 73 1 90.2 J5.4
21. Unit Capacity Factor IUsing MDC Neti 74.6.

40.3 82.2

22. Unit Capacity Factor iUsing DER Net) 71.5 87.0 7 6 . :$
23. Unit Forced Outage Rate 21.4 6.6 6.1
24. Shutdowns Scheduled Over Nest 6 Months tType. Date.and Duration of Each):

Calvert Cliffs 'fo. 2 Pl. int is scheduled for a ,lanned outace startinq netober 14, 1474, and vill be six weeks in duration for overhaul and retueling.

25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units In Test Status (Prior to Commercial Operationi: Forecast Achieved INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCIAL OPER ATION

!  ! (4/77)

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-317 Calvert Cliffs 41 S'IT DATE 10/15/79 COMPLETED B\- S. D. Merson TELEPHONE 301-234-5240

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MONTil DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) g 772 g7 732 2 801 18 729 3

803 39 800 4 734 20 807 3

70; 23 808 6 763 22 809 7 310 23 8I2 8 790 24 310 9 718 25 807 10 6u4 26 734 gg 724 g 745 709 309 12 3 13 7u5 e11 39 14 7"" '0" 30 15 774 31 16 M1 INSTRUCTIONS On this format, list the average daily unit power level in MWe Net for each day in the reporting month. Compute :o the nearest whole megawatt.

(9/77)

/ 348

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 5-318 UNIT calvert Cliffs 42 DATE 10/15/7' S. D. y2rson COMPLETED BY TELEPHONE 301-23--5240 MONT11 Sentenber, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) (MWe Net) 808 324 y g7 2 743 gg S28 3 827 39 171 4 825 000 20 5 925 21 835 6 760 22 S36 7 7"7 23 80" g Ato 24 764 9 -

25 S38 10 26 7" 11 -

27 731 12 28 333 13 29 771 14 112 730 30 15 626 3, 16 736 INSTRUCTIONS On this format. lis he average daily unit power levelin MWe Net for each day in the reporting nonth. Compute to the nearest whole rnegawatt.

f )bt ) (41771

UNIT SilUTDOWNS AND POWER REDUC 110NS DOCKET NO. '" '- 1 1 7 UNIT NAME c il v. rt cittts rio . 1 DATE 10/15/7" COMPLETED BY s . ii . ne rw n REPORT MONT11 9. >r<rbr 1979 TELEPilONE 101 - 2 3'+-5 72 0

-  : c No. Date

- .$g 3 j Y3 Licensee ,E g j". Cause & Corrective h 3g i 2s5 Event p Q Action to 6- y* 5 j 63 Report a mV g Prevent Recurrence 6

79-11 790906 F 9.6 A ilA Cli IflSTRU Reactor tripped on low-steam

,r ene ra tor level due to a failed differential pressure controller on 12 feedwater regulatine valve.

N I .2 3 4 ts F: Forced Reason: Method: Exhibit G -Instructions m S: Scheduled A-Equipment Failure (Explain) 1 Manual for Preparation of Data o B Maintenance ci Test 2-Manual Scram. Enery Sheets for Licensee C Refuelmg 3 Automatic Scram. Event Report (LER) File (NUREG-D RcFulatory Restriction 4.Other (Explain) 0161) 1 -Operator Training & Ucense Examination F Adnurustrative 5 G. Operational En ros (Explam) Exhibit 1 - Same Source 19/77) 110:her (Explain)

DOCKET NO. W-11" UNIT SilUTDOWNS AND POWER REDUC 110NS UNIT NAME ca l ve rt clitis No. 2 DATE 10/15/7

9onrorhor COMPLETED BY s . n. rfe rson REPORT MONT11 1**79 TELEPflONE 101-234-5240

- 5g 3 Y> Licensee ,E v, g, Cause & Corrective No. Date h 3g ( 2sy Event g g'8 Action to H j= 5 j gp3 g Repori a mV g

V Prevens Recurrence 6

79-14 790908 F 140.8 A 1 NA CB Motor X Forced outage due to a failure of the Field B phase capacitor in No. 21B reactor coolant pump motor.

7 ')- 15 7o091') F 16.7 A 1 NA Cil PumpXX Peactor tripped on lo ateam genera-tor level due to loss of 21 main feedwater pump speed controller.

4 N

I 2 3 4 t~ F: Forced Reason: Method:

S: Scheduled Exhibit G - Instructions tn A Equipment Failure (Explain) 1-Manual for Preparation of Data

- B-Maintenance oi Test 2-Manual Scram. Entry Sheets for Licensee C Refueling .1 Aulomatic Scram. Event Report t1 ER) File (NUREG-D-Regulatory Restriction 4 Other (Explain) 0161) 1:-Operatur Traiaing & License Examination F Admimstrative 5 G.Operatmnal Ersur (Explam) Exhibit I Same Source pJ/77) Il Ot her ( E xplain)

10/9/79 REFUELING INFORMATION REOUEST

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 followin; refue'ing: 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 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 22, 1980

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 contmon 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 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 4

177 3c}

10/9/79 REFUELING INFORMATION REQUEST

1. Name of Facility: Calvert Cliffs Nuclear Power Plant, Unit 2
2. Scheduled date for next refueling shutdown: October 14, 1979
3. Scheduled date for restart following refueling: November 21, 1979
4. Will refueling or resumption of operation thereafter require a technical speci-fication change or other license amendment?

A preliminary review of the design and safety analysis indicate that no changes to the Technical Specification or other amendments are required and that there will be no ur. reviewed safety questions as defined by 10 CFR 50.59 involved with this rel G d core design.

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

August 22, 1979 (if required).

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) 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

^/ 353

SU!1?tARY OF U' LIT 1 GPERATIrlG EXPERIE lCE - SEPTE:1BER 1979 9/1 At the beginning of this reporting period Unit I was operating at 815 :t'le. Peactor Power was limited to 97" due to in-core Power Distribution problems. At 0300, load was decreased to 735

!Rle to investicate salt water leakage into the main condenser.

Full load opera'.M (335 lle) was resumed at 1300 after plugging om condenser tube.

9/4 Load was decreased at 1400 to 665 !?.le to investigate salt water leakage into the main condenser.

9/5 Load was increased to capacity (835 ff.le) at 0400 after plugging one condenser tube.

9/6 Decreased load to 715 Kle at 0015 to investigate salt water leakage into the main condenser. One condenser tube was plugged and full load operation (835 :o.le) was resuned at 0900. At 2357 the reactor tripped on low steam generator level due to a failed differential pressure controller on 12 feedwater regulating valve.

9/7 The reactor was brought critical at 0625 and the unit paralleled at 0933. Full load operation (320 ! ale) was resuned at 2130.

9/9 At 0600 Load was decreased to 715 7.le to investigate salt water leakage into the main condenscr. Load was increased to 820 :UE at 2020. At 2330 load was decreased to 715 !?!e to investigate salt water leakage into the main condenser.

9/11 Start!d increasing load at 1630 after plugging one condenser tube and at 2120 load was reduced to 735 Ne to investigate salt water leakage into the nain condenser.

9/12 Load was increased to 815 t4!e at 2400.

/ 354

9/15 Reduced load to 730 f t'le at 1331 to investigate salt water leakage into the main condenser.

9/16 Increased load to caoacity (235 file) at C500.

9/17 At 1200 load was decreased to 705 ' Ele to investigate salt water leakage into the main condenser.

9/18 Full load operation (335 t!e) was resumed at 1300 af ter nlugging three condenser tubes.

9/25 Cecreased load to 755 fUe at 2245 to investicate salt water leakage into the main condenser.

9/26 One condenser tube uas plugged and increased load to caoacity (335 file) at 1800. At 2200, reduced load to 685 ftle to investigate salt water leakage into the main condenser.

9/27 At 0800 load was increased to caoacity (335 'tle).

9/28 Reduced load to 825 INe to work on the nomal level control valve for 163 Feedwater heater. Full load oceration (345 5!e) was resumed at 1320.

9/30 At the end of this recorting neriod, I' nit I was coerating at 345 'He with the reactor at 100" power.

s ,

,3 , , . , -

/ 333

SIR!'!ARY OF IFlIT 2 OPERATI'iri EXPERIE lCE - SEPTE:1BER 1979 9/1 At the beginning of this reporting period Unit 2 was ocerating at 730 ltle. Reactor oower was limited to 33", to investigate salt water leakage into the main condenser. At 0700, full load oneration (345 !?le) was resumed after one condenser tube was plugged.

9/2 At 0330 load was reduced to 585 itle to align control element assembly

42. Load was increased to canacity (345 !Ue) at 1000. At 1430 load was decreased to 815 'tle due to in-core alams. Full load operation (355 '"le) was resumed at 2355.

9/6 Decreased load to 795 f tle at 0430 to investigate salt water leakage into the main condenser.

9/7 Plugged one condenser tube and increased load to capacity (355 ffle) at 0900. At 1801 the reactor trioned on loss of flou due to a surge capacitor failure on 213 reactor coolant oumn.

9/10 At 0450 the unit was in cold snutdown. Started draining the reactor coolant systen at 1830.

9/11 Secured draining the reactor coolant system at 1015.

Connenced filling the reactor coolant system at 1336.

Secured filling the reactor coolant system at 1447. At 1815 connenced reactor coolant system heatuo.

9/14 The reactor was brought critical at 0310. The reactor was shutdown when control element assembly 5 dropoed into the core at 0631. 'The reactor was again brought critical at 1210 and the unit paralleled at 1447. Molding load at 600 ?le to investigate saltwater leakage into the main condenser.

9/16 Increased load to capacity 260 IEle at 2200 after olugging two con-censer tubes. '1

/ }g6

9/19 At 0440, the reactor tripoed on low steam generator level due to loss of 21 main feedwater punp speed controller. The reactor was brought critical at 1930 and the Unit paralleled at 2125.

9/20 Resuned full load operation (365 Mie) at 2100.

9/23 Decreased load to 755 Mle at 2200 to investigate saltwater leakage into the main condenser.

9/24 Pluggt d two condenser tubes and increased load to caoacity (865 'tle) at 1740.

9/26 At 0545, decreased load to 710 'fle due to intake screen problens.

Increased load to 365 Mle at 2200.

9/27 Reduced load to 710 5!.4e at 0800 to investigate saltwater leakage into the nain condenser. Resumed full load operation at 2100.

9/29 At 1400, reduced load to 725 f t.le to investigate saltwater leakage into the main condenser.

9/30 At the end of the recorting period load was being increased to capacity (865 Kle), after olugging one condenser tube.

[ .h b [

SAFETY-RELATED ftAINTENANCE UNIT I GROUP If.C MONTH SEPTEftt'ER YEAR 1979 CC Ln MALFUNCTION m SYSTEM OR COMPONENT MR N0. - DATE CAUSE RESULT CORRECTIVE ACTION

s. t Safety Injection Tank IC-79-066 5/16/79 Pressure instrument Received out of spec. Performed func- '

12A Pressure Indication out of adjustment reading during loop tional test and {_

1-PI-331 calibration adjusted instrument Component Cooling Heat 0-79-1765 6/13/79 The valve hand The valve would be Adjusted valve '

Exchanger 1-CV-5208 controller was out open with the valve hand controller Saltwater Outlet of adjustment and hand controller out- and adjusted supply Valve was not receiving a put on zero air to the control-proper air signal ler 12 Main Steam Isolation 0-79-1813 6/18/79 Air and dirt in in- Hydraulic fluid reser- Bled air and dirt Valve Hydraulic Package strument sensing line voir level gauge not from sensing line reading properly '

11 Main Steam Isolation 0-79-1523 5/23/79 Gauge was out of #11 MSIV-#2 high pres- Adjusted gauge to Valve Hydraulic Package adjustment sure surge accumulator proper zero and

  1. 2 High Pressure Surge gas pressure gauge was cleaned gauge Accumulator Pressure indicating wronq snubber  ;

Gauge  ;

SAFETY-RELATED MAINTENANCE UNIT I GROUP ELECTRIL SHOP MONTil YEAR SEPTEMBER 1979 cw tn

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

l'ain Steam Isolation E-79-104 6/13/79 Valve operator limit Erratic operation of Adjusted limit Valve Bypass switches out of adjust- valve switches, replaced 1-MOV-4045 ment, damaged flexible flexible conduit conduit, close torque and connectors, and switch had dirty cleaned close torque contacts switch contacts

4 SAFETY-RELATED MAINTENANCE UNIT I GROUP IAC MONTH SEPTEMBER YEAR 1979 c) e MALFUNCTION m SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION i rs-r Reactor Coolant System / 0-79-2069 7/10/79 Level transmitters Greater than 10 inch Performed func-Pressurizer Level out of adjustment deviation between the tional tests on Controller Instrument two instruments transmitters and 1-LIC-110X readjusted 1-LIC-110Y .

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SAFETY-RELATED MAINTENANCE UNIT II GROUP MACHINE SHOP MONTH SEPTEMBER YEAR 1979 MALFUNCTION -

SYSTEM OR COMPONENT MR NO. - DATE CAUSE RE5dLT CORRECTIVE ACTION st) m 21 Charging Pump 0-79-2423 8/10/79 Cyclic fatigue Excessive packing Replaced packing and leakage plungers.

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22 Charging Pump 0-79-1953 7/13/79 Cyclic fatigue Excessive packing Replaced packing and leakage plungers.

21 hain Steam Isolation 0-79-1680 7/31/79 Solenoid valve Main steam isolation Replaced solenoid Valve 2-SV-4044 sticking valve took too long valve.

to close during test 21 Charging Pump 0-79-2670 9/6/79 Cyclic fatigue Excessive packing Replaced packing and leakage plungers 23 Charging Pump 0-79-2132 7/18/79 Broken valve stem on Unable to charge Replaced bladder and Desurger bladder bladder associated seals.

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