ML19351E976

Monthly Operating Repts for Nov 1980

ML19351E976
Person / Time
Site:	Calvert Cliffs
Issue date:	12/15/1980
From:	Merson S BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19351E973	List: ML19351E972 ML19351E976
References
NUDOCS 8012190630
Download: ML19351E976 (16)

Text

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O OPERATING DATA REPORT DOCKET NO.

50-317 DATE ' ' 1 5 / 8 0 COMPLETED BY s.D.Merson TELFPHONE 301-737-5364 OPERATING STATUS CaIvert Clitis No. I Notes

1. Unit Name:

N vember, 1980

2. Reporting Period:

2.700

3. Licensed Thermal Power tMWt):

9IO

4. Nameplate Rating (Gross MWel:

845

5. Design Electrical Rating (Net MWe):

845

6. Maximum Dependable Capacity (Gross M' Vel:

810

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings tirems Number 3 Through 7)Since Last Report.Give Reasons:

9. Power Level To Which Restricted. If Any (Net MWe):

10. Reamm For Restrictions.lf Any:

This Month Yr.-to-Date Cumulative 720 8,040 48,805

11. Hours In Reporting Feriod 0.0 e,421.1 38,860.i

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours 0.0 38.3 1,098.8

14. Hours Generator On.Line 0.0 6,350.7 38,052.7

15. Unit Reserve Shutdown floors 0.0 0.0 0.0

16. Gross Thermal Energy Generated IMWH) 0.0 15,229,803 90,566,792

17. Gross Electrical Energy Generated (MWH1.

0.___._.

4,781.703 29.594,233

-2,460 4,540,582 28,189,788

18. Net Electrical Energy Generated (MWHp 0.0 79.0 78.0

19. Unit Service Factor 0.0 79.0 78.0

20. Unit Availability Factor 0.0 o9.7 ei.o i

21. Unit Capacity Factor iUsing MDC Net 1 0.0 66.8 68.4

22. Unit Capacity FactoriUsing DER Net) i 0.0 2.9 8.1 l

23. Unit Forced Outage Rate

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

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

26. Units In Test Status (Prior to Commercial Operationi:

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8012190

OPERATLNG DATA REPORT DOCKET NO.

50-318 DATE 12/15/30 COMPLETED BY s.D.Merson TELEPHONE 301-787-5364 OPERATING STATUS Calvert Cliffs No. 2 Notes

1. Unit Name:

November, 1980

2. Reporting Period:

2, wo

3. Licensed Thermal Power (MWt):

9II

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

860

6. Maximum Dependable Capacity (Gross MWet:

825

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (ltems Number 3 Through 7) Since Last Report. Gi+e Reasons:

a

9. Power Level To Which Restricted.If Any (Net MWe):

10. Reasons For Restrictions. If any.

J

.m-

=

This Month Yr.-to-Date Cumulative 720 8,040 32,t60

11. Hours in Reporting Period

12. Number Of Hours Reactor was Critical 720.0 7,730.9 27.675.8

13. Reactor Reserve Shutdown Hours 0.0 28.7 441.8

14. Hour Generator On-Line 720.0 7,684.5 27,293.1 15 Unit Reserve Shutdown flows 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1.701,199 19.146.618 67.390,850

17. Gross Electrical Energy Generated IMWHI 355,634 6,273,875 22,279,095 i

18. Net Electrical Energy Generated (MWH) 530,057 5,988,931 21,245,951

19. Unit Service Factor 100.00 95.6 84.9

20. Unit Availability Facroe 100.00 95.6 84.9 89.2 90.3 81.1

21. Unit Capacity Factor IUsing MDC Net t

22. Unit Capacity Factor IUdng DER Nett 87.1 88.1 78.2

23. Unit Forced Outage Rate 0.0 1.2 5.4

24. Shutdowns Scheduled Oser Next 6 Months tType. Date.and Durasian of Each t:

scheduled for a planned outage starting January 2, 1981, untti

? Plant March 2, 1981, for refueling, unit general inspection and TMI Modifications.

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

26. Units in Test Status (Prior o Commerrial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

.. x

AVERAGE DAILY UNIT POWER LEVEL 50_317 DOCKET NO.

Calvert Cliffs DATE 12/15/80 S.D.Merson COMPLETED BY

~

TELEPHONE

~

N vember, 1980 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(ywe.Nei,

^

I 17 2

18 3

19 4

~

20 5

21 6

22

~

~

7 23 8

24

~

9 25 l

10 26

~

l II 27 l

(

28 l

12 13 29 I4 30 15 3

I6 l

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

l (9/77)

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AVER AGE DAILY UNIT POWER LEVEL 50-318 DOCKET NO.

Calvert Cliffs Nc DATE 12/15/80 S.D.Muson COMPLETED BY 301-787-5364 TELEPHONE November, 1980 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER ACE DAILY POh ER LEVEL (MWe Net p tMWe Net) 1 422 695*

37 2

185 gg 737 769 739 3

g 4

848 20 700 848 698 5

gg 849 698 6

22 7

849 698 23 351 697 g

851 700 9

850 700 10 851 700 gg 851 700 12 849 634 13 845 634 14 IS 825 3g 670 16 INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting month. Ciunpute to the nearest whole nwgawatt.

(9/771 l

~.

UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-317 UNIT NAME calvert utifts Al DATE 12/15r80 0N

" ^ " ' ' ~ "

REPORT MONTH 'lemh..r 1980 TELEPHONE _1n1_7a7216c w.

E E

,!g "h

jY3 Licensee Eg g e,,

Cause & Corrective l

No.

Date k

52 4

.3 ~$

Esent g

Q Action to f f 5

j #3 g Report a mv Prevent Recuracnce g

d 80-11 801018 5

720.0 C

1 XX ZZZZZ Refueling, Unit General Inspection and THI Modifications.

I 2

3 4

F: Forced Reason:

Method:

Exhibst G - Instructions S: Scheduled A Equipment Failure (Explain)

I Manual for Preparation of Dasa B. Maintenance of Test 2-Manini Scram.

Entry Sheets for Licensee C Refueling 3 Autonutic Scram.

Event Report (LE RI File INURiG-D Regulatory Restriction 4 Olher (Explaini 0161)

E Operator Training & License Exansnation F-Adninistrative 5

G Operational Errus (Explain)

Exhibit 1 Same Source 19/77)

Itother (Eaplain)

UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-318 UNIT NAME Calvert Chifts No. 2 DATE 17/15/80 REPORT MONTH November, 1980 COMPLETED BY

.S. D. Ff o r e n n TELEPHONE 301-787-5364 "5

h 3E

'h h E$

Licensee

,q,,,

84 Cause & Corrective No.

Date

{

3g g

jg5 Evens s '1 3

Action to

$E 5

jdg Report

• E0

[L Prevca: Recurrence d

i 80-15 801101 5

56.0 11 XX ZZZZZZ Fuel Conservation, Capacity Availabit on Demand.

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2 3

4 F: Forced

. Reason:

Method:

Exhibie G - Instructions S: Scheduled A Equiprnent Failure (Explain)

I Manual for Preparation e4 Dara B-Maintenance or Test 2 Stanual Scram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

Event Report (LE R) Fde t NUREG-D Regulatory Restriction 4-Other (Explain) 01611 E-Operator Training & Ucense Examination F Adnunistrative 5

G-Operational Eirus (Explain)

Extiibit I Sane Source (9/77)

Ilfhher (Explain) l l

REFUELING INFORMATION REQUEST 1.

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

Scheduled date for next Refueling Shutdown: April 16,1982 3.

Scheduled date for restart following refueling: December 15,1950' 4.

Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?

Resumption of operation af ter 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 reshuf fled core.

5.

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

August 29, 1930 November 4,1980 (Supplemental Submittal) 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 assemblics (a)in the core and (b)in the spent fuel storage pool.

(a) 217 (b) 456

- Spent Fuel Pools are common to Units I and 2 3.

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 assemblics.

1358 Licensed 1028 Currently Installed 472 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.

l October,1985

• Information changed since last report.

l

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4 REFUELING INFORMATION REQUEST 1.

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

2.

Scheduled date for next refueling shutdown: January 2,1931.*

3.

Scheduled date for restart following refueling: February 12,1931 4.

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

Resumption of operation af ter 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 reshuf fled core.

5.

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

December 4,1980*

6.

Important licensing 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) 456 4

Spent Fuel Pool is common to Units 1 & 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.

1358 Licensed i

1028 Currently Installed 472 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,1985

• Information changed since last report.

4

SUMMARY

OF UNIT I OPERATING EXPERIENCE - NOVEMBER 1980 11/1 At the beginning of this reporting period Unit I was shutdown for its 4th scheduled refueling outage.

11/3 Fuel handling operations began at 1335.

11/20 Completed fuel handling operations at 1047.

11/30 At the end of this reporting period, Unit I was still shutdown for its 4th scheduled refueling outage.

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SUMMARY

OF UNIT 2 OPEllATING EXPERIENCES - NOVEMBElt 1930 11/1 At the beginning of this reporting period Unit 2 was operating 710 MWe with the reactor at 33% power, while investigating saltwater leakage into the main condenser. At 0800 load was decreased to 415 MWE for fuel conservation.

Plugged one leaking condenser tube.

11/3 Load was increased to capacity (365 MWe) at 1045.

11/14 Started reducing load for the power coastdown procedure in preparation for the 3rd refueling outage.

11/16 At 0300 Control Element Assembly (CEA) I dropped into the core. Reactor power was immediately reduced to less than 70% in accordance with the Technical Specifications. CEA 1 was withdrawn back to its group at 0406. Load was increased to 745 MWe at 1415.

11/20 At 1100 load was reduced to 670 MWe to investigate saltwater leakage into the main condenser. Load was increased to 730 MWe at 2000 af ter plugging I condenser tube.

11/28 Decreased load to 665 MWe at 1200.

11/30 At the end of this reporting period Unit 2 was operating at 665 MWe with the reactor at 76% power, being limited by the power coastdown procedure in preparation for the third refueling outage.

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SAFETY-RELATED MAltlTENAf!CE UrtIT OrlE GROUP I&C SHOP MONTil fl0VEMBER YEAR _1980 f tALFl!NCTION l

SYSTEM OR COMPONENT MR NO. - DATE CAUSE RZSULT CORRECTIVE ACTION '

1. 12 Control Room Air it-80-3241 Temperature Controller Air Conditioning Unit Adjusted the Conditioner, 10-1-30 0-TC-5343 was out of would shut itself down.

Temperature Controlldr' adjustment.

0-TC-5343.

1. 11 Control Room Air 0-30-4269 Temperature Controller Air Conditioning Unit Adjusted the Tempera-Conditioner.

10-26-30 0-TC-5342 was out of would not start.

ture Controller I

adjustment.

0-TC-5342.

0

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SAFETY-RELATED MAINTENANCE UNIT Tuo GROUP

, Ar mann MONTil N0vrnaro YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACT!nt:

Reactor Protective 0-80-4703 Defective 15 VDC Power liigh Voltage Alann from Replaced the Ib VDC e System / Channel "B" Uide 10-28-80 Supply llodule.

Reactor Protective Power Supply.

Rang Nuclear Instru-System.

mentation.

Engineered Safety IC-30-2107 Defective Signal Isolator Low Output Signal from Replaced the Signal Features Actuation 10-21-80 2-E/E-5313A.

Channel **ZD" Safety In-Isolator System / Signal Isolator jection Actuation System 2-E/E-5313A.

2-E/E-5313A.

Drauer.

Channel "A" Uide Range IC-79-2105 Defective Detector and Channel "A" Wide Range Replaced the Detector

, Nucl:ar Instrumentation 10-23-79 Pre-amplifier.

Detector failed to pass and Pre-amplifier.

• Detector Functional Test.

2-NI-001.

Incore Detectors IC-79-2119 End of Life.

Detectors not functioning Replaced Detectors D-3, T-2, W-6, R-6, T-9, 11-2/-79 properly.

0 s. T-2, 4-6, R-6, X-7, X-17, V-15. C-16.

T-9 X-7, X-17. V-15, C-16.

SAFETY-RELATED MAINTENANCE UNIT GUE GROUP "E" SHOP MONTH uovnuro YEAR 1980 t1ALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT,_

CORRECTIVE ACTION i

1-M1V-660 0-80-4525 Limit Switch Out of Valve would not close Adjusted the Limit

. Safety injection Pump 10-22-60 Adjustment.

tight ennugh.

Switcn.

l Mini Flow Valve.

___________., =

1. 14 Containment Cooler.

0-30-4518 Defective Relays 42it and Cooler Unit would not Replaced Relays 10-22-u0 42L.

snift to Low Speed.

4211 and 42L.

I lSafetyIn.iectionPump l *10V-659 0-80-4524 Limit Switch Out of Valve would not close Adjusted the Limit 10-22-30 Adjus tment.

tight enough.

Switch.

Mini Flow Valve.

120 VAC Vital Instrunent 0-30-4196 Cabinet Fan in Engineeret Ground on the all 120 VAC Replaced the Cabinet Bus #11.

9-29-80 Safety Features Cabinet Vital Instrument Bus.

Fan.

g IC67L was grounded.

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' #24 Battery Charger.

E-80-182 Defective Relay PLR-1.

PLR-1 Relay would not Replaced the Relay.

I 11-4-83 function properly.

z______

1. 11 Main Plant Exhaust U-80-4718 Defective Trip Coil.

Breaker ualfunctioned Replaced the Trip Fan Breaker 11-2-80 causing damage to the Coil and Secondary 52-1117.

Breaker Secondary Contact Contact Block.

Llock.

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.I SAFETY-RELATED MAINTENANCE UNIT ONE i

GROUP "E" SHOP MONTH unvEM3ER YEM 19d0

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[

l MALFUNCTION 2

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

l-M0V-6200 0-30-4563 Stationary Contact on Valve would not operate Tightened the Sta-l U-l Containment 10-25-80 Torque Switch was loose.

from Remote Hand Switch.

tionary Contact and l Fire Protection cleaned Torque Switcn Isolation Valve.

Contacts.

l 4 KV Bus 11 under Voltage E-80-208 Spring Tension on K-3 Breaker would not trip on Adjusted Relay K-3 Relay K3.

11-19-80 Relay was out of adjust-under Voltage Condition.

Spring Tension.

ment.

p 012 Main Vent fan Breaker 0-30-4719 Defective Closing Coil Fan would not start.

Replaced the Closing g52-1417.

10-29-80 in Breaker.

Coil.

480 VAC Bus 14A Feeder E-80-167 Defective Amntector.

Anptector would not trip Replaced the Amptec-Breaker 10-26-80 on long time over current.

tor.

52-1412.

1

1. 11 Battery Charger E-30-lG3 Defective Amptector.

Anptector would not trip Replaced the Amptec-

. Breaker 10-23-00 on long time over current.

tor.

I 52-1111.

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o SAFETY _RELATED MAltlTENANCE UtlIT TLIO GROUP "E" Sil0P 1

MONTil fl0VEMBER YEAq 1980 fMLFUNCTI0ft l

SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACT!4':

1. 21 Containment Cooling -

0-80-4754 Defective Starter Ter-Fan tripped while running Replaced Starter Fan.

11-1-30 minal Blocks.

in Fast Speed.

Terminal Blocks l

T5 and T1.

1. 11, 12, 21 0-80-4514 Defective Annunciator Ground on #11, 12, 21 Replaced the 125 VDC Buses.

10-22-80 Card in K32 Circuit.

125 VDC Buses.

Annunciator Card.

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1 SAFETY-RELATED MAIriTEllA21CE Uf1IT One 4

GROUP Machine Shop

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f40!lTil November YEAR-1930' LER OR MALFUriCTIOil l

SYSTEM OR CO'fPO! LENT

!.m NO. - DATE Of)TAGE CAUSE 1

RESULT CORRr'CTIVE ACTIO!i i

1-CV-3828 M-79-524 Damaged seat Leakage past Rpplaced seat.114cr.

liner seat with valve shut.

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1-CV-6'48 M-80-047' Damaged valve Leakage past' valve Eep)1 ced seat 31 '

4 seats.

seat causing safe-riag, cage,j,apd ty injection tank stem.

I- (;

water level to

,,' e drop.

j; 1

Number 11 Component M-79-506 Continuous' Pack-Overload on misc.

Replaced packing Cooling Pump

.ing plan,d leak-waste system.,

glands with meciza,nical seals <

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