ML19269D156

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Monthly Operating Rept for Jan 1979
ML19269D156
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 02/15/1979
From: Merson S
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19269D154 List:
References
NUDOCS 7902270397
Download: ML19269D156 (17)
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Text

,

4 OPERATING DATA REPORT DOCKET NO.

$0-317 DATE 2/16/79 COSIPLETED BY rspn O -$ -5240 TELEPllONE OPERATING STAT US

1. Unit Name: Calvert Cliffs No. 1
2. Reporting Period:

January, 1979

3. Licensed Thermal Power (MWt):

97ty) 910

4. Nameplate Rating (Gross SlWe):

8hd

5. Design Electrical Rating (Net MWe):

Ob5

6. Mav.imurr. Dependable Capacity (Gross MWeI:

810

7. Maximum Dependable Capacity INet MWe):
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
9. Power Lesel To which Restricted.If Any (Net Mbe):

None

10. Reasons For Restrictions.lf Any:

N/A This Month Yr.-t o-Da t e Cumulative

11. flours in Reporting Period 7hh 7hh 32.7h9
12. Number Of 11ours Reactor was Critical 326.4 32G.4 26.hlh.1
13. Reactor Resene Shutdown llours 122.7 122.7 1.016.3
14. Ilours Generator On Line 300.8 308.8 25.853.8
15. Unit Resene Shutdown lim rs 0.0 0.0 0.0
16. Gross Therma! Energy Generated 1MWil) 690.130 690.130 61.960.33h.h
17. Gross Electrical Energy Generated (MWill 216.720_ ____.

216.728 20.603.063

18. Net Electrical Energy Generated (MWill 203.17h 203.17h 19.658.162 bl.5 hl.5 78.9-
19. Unit Service Factor bl*6 kl.5 78.9
20. Unit Availability Factor 33 7 33.7 7h.1
21. Unit Capacity Factor (Using MDC Net)
22. Unit Capacity Factor (Using DER Net) 32.3 32.3 71.0 58.5 58.5 9.0
23. Unit Forced Outage Rate
24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each t:

, Calvert Cliffs No.1 is scheduled for a planned outane startine Aoril lh.19E and will be six week's in duration for connral inanne t.4 nn and refueling.

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

Forecast Achieved INITIA L CRITICA LITY INITI AL ELECTRICITY COMMEkCI AL OPER ATION vso227o2A1 (9/77)

OPERATING DATA REPORT DOCKET NO.

50-318 DATE 2/1$/73 COSIPLETED BY S. D.

4erson TELEPfl0NE 301-211-52h0 OPERATING STATUS N

S I. Unit Name: Calvert c14rr, nn_ 9

2. Reporting Period:

Ja.nu ry. 1979

3. Licensed Thermal Power (MWt):

27tv)

4. Nameplate Rating (Gross MWe):

911

5. Design Electrical Rating (Net MWe): 8h5 Ob5
6. Masimum Dependable Capacity (Gross MWel:

810

7. Maximum Dependable Capacity (Net MWe):
8. If Changes Occur in Capacity Ratings (items Number 3 Through 7)Since Last Report.Gise Reasons:
9. Power Lesel To which Restricted. If Any (Net MWe).

None N/A

10. Reasons For Restrictions. If Any:

This Month Yr.-t o.Da t e Cumulative 7hh 7hh 16.10h

11. liours in Reporting Period 55h.1 55h.1 13.5h6.6
12. Number Of flours Reactor Was Critical
13. Reactor Resene Shutdown liours 0.0 0.0 219.h
14. liours Generator On.Line 529.9 529.9 13,% 1.7
15. Unit Reane Shutdown llours 0.0 0.0 0.0
16. Gross Thermal Energy Generated tMWil) 1,307.688 1.307.688 32.191.70h.6
17. Gross Electrical Energy Generated (MWH)

_ hkl2921L _ _.

hhl.92h 10.694.996 2

18. Net Electrical Enargy Generated (MWil) h20.021 h20.021

.10 188 040 71.2 71.2 82.8-

19. Unit Senice Factor 71.2 71.2 82.8 2t). Unit Availability Factor 69.7 69.7 78.1
21. Unit ~;pacity Factor (Using MDC Net)
22. Unit Capacity Factor (Using DER Net) 66.8 66.8 7h.9
23. Unit Forced Outage Rate 8.1 8.1 6.0
24. Shutdowns Scheduled Oser Nest 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 A chiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (9/77)

4 AVER AGE D AILY UNIT POWER LEVEL DOCKET NO.40-317 UNIT Calvert Cliffs #1 DATE 2/15/79 COMPLETED BY S. D. Merson TELEPilONE 301-23h-52h0 MONTil Jn mnn, 1979 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe NetI (Mwe. Net )

1 17 2

IS 19 321 3

20 727 4

699 5

21 380 6

22 7

23 350 578 8

24 25 787 9

10 26 797 kl 27 797 12 28 71h 13 29 803 14 30 805 15 3

807 16 INSTRUCTIONS On this format. list the aserage daily unit power levelin MWe Net for each day in the reportirg month. Compute to the nearest whole megawatt.

(9/77)

AVERAGE D ALLY UNIT P0hER LEVEL DOCKET NO.60-318 UNIT Cnivert Cliffs #2 DATE 2/16/79 COMPLETED BY S. D. Merson TELEPilONE 301-23h-52ho MONTil Jnnuncy; 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net )

1 85 0 i7 806 2

851 is Bob 3

861 19 806 4

861 20 33 5

851 21 6

1103 22 7

267 23 g

716 24 9

7h9 25 766 10 26 gi 771 27

~

l2 781 23 680 80h 835 i3 29 14 805 039 30 a5 801 3

8h9 16 790 INSTRUCTIONS On this format, list the average daily unit power leselin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

DOCKET SJ.

50-317 UNIT SIIUTDOWNS AND POWER REDUCTIONS Calvert Cliffs #1 UNIT NAME DATE 2/15/79 COMPLETED BY A-D. Merson REPORT MONT11.innnwy, 1979 TELEPIIONE 301-23h-Oho e.

.!?

3 Y

Licensee Eg Cause & Corrective 3g js5 Event s?

E'8 Action to No.

Date c

jE 5

5gF Repori

  • EV EV Prevent Recurrence f

v 5

78-19 781217 F

h30.5 A

h N/A HA ZZZZZZ Forced outage due to vibration on the high-pressure turbine. Internal investigation revealed damage to the first stage high-pressure turbine blades.

79-1 790122 F

h.7 H

3 N/A HH ZZZZZZ Forced outage due to a unit trip caused by high water level in #12B feed water heater.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S: Sched u!cd A Equipment Failure (Explain)

? -Manual for Preparation of Data B-Maintenance ci Test 2 Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Ot her ( Explain) 0161) 1:-Operator Training & Lic-ose Examination F-Administrative 5

G-Operational Er ror (Explain)

Exhibit I - Same Source (9/77)

Il-Ot her ( E xplain)

DOCKET NO.

50-118 UNIT SilUTDOWNS AND POWER REDUCTIONS Galvert Cliffa #2,

UNIT NAME DATE 2 / 18s / 7 9 COMPLETED BY S. D. Herson REPORT MONT11

.inmm 7, 1_979 TELEPiiONE 301-23h ohn C

C 3?

3

$ E~

Licensee

,E -t, f~.

Cause & Corrective No.

Date g

3g

{

js5 Esent a 'y e.8 Action to

$E 5

3. g :!s-Report n (E U 5L Prevent Recurrence v

6 79-1 790106 F

22.6 A

1 (9-001 CB PIPEXX Forced outage due to excessive reactor coolant system leakage caused by a cracked weld on #21A reactor coolant pump middle seal pressure sensing linc 72-2 790120 F

2h.O A

2 79-003 CB PIPEXX Forced outage due to high temperature on the lower seal of #22A reactor coolant pump. Inspection revealed a cracked weld on the lower seal press-ure sensing line of #22A reactor coolant pump.

79-3 790121 s

167.5 B

h N/A ZZ ZZZZZZ Status changed from forced to se,. adulec to perform safety related testing and to replace the seals on #21B and 22A reactor coolant pumps.

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 ci Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Ot her ( Explain )

0161) 1: Operator Training & License Examination F Administrative S

G-Operational Er ror ( Explain)

Exhibit I - Same Source (9/77)

Il-Ot her ( E xplain)

2/15/79 REFUELING INFORMATION REQUEST 1.

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

Scheduled date for next Refueling Shutdown April 21, 1979 **

3.

Scheduled date for restart following refueling May 29, 1979 **

h. Will refueling or resump+ ion 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 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 nurber of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 217 (b) 228*

  • 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 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.

2/15/79 REFUELING INFORMATION REQUEST 1.

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

Scheduled date for next Refueling Shutdown October 6, 1979 3.

Scheduled date for restart following refueling November lh, 1979 **

h.

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 bo such as to allow operation of the plant with a fresh reload batch and reshuffled c ore.

5.

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

July 6, 1979 6.

Important licensing considerations associated with zufueling-Reload fuel will be similar to that reload fuel inserted into tne Cycle 3 of Unit 1.

7.

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

(a) 217 (b) 228*

  • 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, loS6 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, 1933 Information has changed since last monthly report.

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE JANUARY 1979 1/1 At the beginning of this reporting period, Unit I was shutdown and the reactor cooled down for removal of damaged main turbine first stage high pressure turbine blades.

1/17 Reactor coolant system heatup commenced at 0205.

1/18 The reactor was brought critical at 0850 and the unit was paralleled at 2144 1/19 The ma;n turbine was taken off line at 0244 to conduct a turbine overspeed trip test. The unit was reparalleled at 0327.

1/20 Load was increased to 830 Kle.

1/21 Load was reduced to 735 MWe at 0005 due tc a steam leak on the high pressure turbine casing.

1/22 At 0957 the reactor tripped on loss of load when the main turbine tripped due to a high water level in 12B feed water heater. The reactor was brought critical at 1136 and the unit paralleled 1139.

Load was limited to 258 IWe due to steam leakage from main turbine high pressure casing.

1/23 Load was increased to 660 fWe at 1800 after reducing the steam leak.

1/24 Load was reduced to 400 R4e at 1400 to accommodate repairs to the main turbine high pressure casing.

1/25 Load was increbsed to 830 fWe at 1600 after completing temporary repairs to the nain turbine high pressure casing. Reactor power was limited to 35% by the Environmental Technical Specification 10 F limit on nain condenser circulating water AT.

1/28 Load was decreased to 700 tUe at 0305 to investigate salt water leakage into the m W condenser.

1/29 Load was increased to 8% Kle at 0030 after the salt water leak disappeared.

1/31 At the end of this reporting period, Unit 1 was coerating at 843 fWe with the reactor at 97% power, reactor power being limited by the Environmental Technical Specification 10 F limit on main condenser circulating water AT.

SUMMARY

OF UNIT 2 OPERATING EXPERIENCE JANUARY 1979 1/1 At the beginning of this reporting period, Unit 2 was operating at 887 MWe with the reactor at 100% power.

1/6 The unit was taken off line at 1342 to locate the source of reac-tor coolant system leakage in excess of Technical Specification limits. The reactor was maintained critical. The source of the reactor coolant system leakage was detennined to be a cracked weld on 21A reactor coolant pump middle seal pressure sensing line.

The cracked weld was isolated at 1448.

1/7 While starting up the main turbine it was discovered that main turbine governor valve #4 was binding and would not stroke prop-erly. After failing to correct the binding problem it was decided to place the unit back in service with governor valve #4 shut.

The unit was paralleled at 1218 1/8 Load was increased to 775 MWe.

1/12 Load was increased to 837 Mle.

1/20 The reactor was manually tripped at 0143 due to a high temperature alarm on 22A reactor coolant pump lower seal. Cool down of the reactor coolant system to repl ce 22A reactor coolant pump seal commenced at 2015.

1/26 Reactor coolant system heatup commenced at 1349.

1/27 The reactor was brought critical at 2340.

1/28 The unit was paralleled at 0115 and began increasing load to 868 MWe.

1/30 Increased load to 885 M4e.

1/31 At the end of the reporting period Unit 2 was operating at 894 FMe with the reactor at 100% power.

Page 1 of 2 SAFETY-RELATED MAINTDIANCE UNIT 1

GROUP MECilANICAL MONTH JANUARY YEAR 1979 MALMJNCTION

__ SYSPEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION 12 Switchgear Room 0-77-2131 5/14/78 Malfunctioning solenoid Compressor shut down on Replaced defective A/C Compressor valve 1-SV-5427 low suction pressure solenoid 12 Charging Pump 0-78-3131 10/7/78 Nomal end of life Secondary packing leak Replaced packing (packing) and plungers 12 Charging Pump 0-78-3276 10/19/78 Nomal end of life Primary packing leak Replaced packing (packing) and plungers 12 Charging Pump 0-78-3016 9/24/78 Broken seal water line Loss of seal water level Repacked pump and replaced seal water line 11 MSIV Hydraulic 0-78-3251 10/17/78 Discharge relief valve Pump discharge pressure Rebuilt discharge Package - li.P. Oil lifting at 2900 psi.

only reached 2900 psi relief valve Pump

Dage 2 of 2 SAFHfY-RELATED MAINTENANCE UNIT 1

GROUP MECHANICAL (CONT'D)

MONTH JANUARY YEAR 1979 MALFUNCTION SYfifEM OR C0!PONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION 1-RV-150 0-78-1791 6/1/78 Boric acid had corroded Valve body / bonnet Replaced with a new 12 Boric Acid Sterage the valve severely leakage valve Tank Recirc Relief

SAFETY-RELATED MAINTENANCE Page 1 of 3 UNIT 2

GROUP MECHANICAL MONTH JANUARY YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION 21B Reactor Coolant M-78-3167 7/5/78 Vibration fatigue Cracked weld on seal Performed weld Pump pressure sensing line repairs 21 Charging Pump 0-78-303 1/23/78 Vibration fatigue Cracked weld on suction Perfomed weld Suction Line relief valve piping repairs 21 Charging Pump 0-78-3367 10/24/78 Failed Bladder Bladder would not Replace bladder Desurger maintain charge and associated 0-rings 21 Charging Pump 0-78-4091 12/11/78 Stuffing box wear Primary packing leak Replaced stuffing box and packing 23 Charging Pump 0-78-3833 11/16/78 Broken charging fitting Could not recharge Installed bladder Desurg::r bladder with redesigned fitting.

Page 2 of 3 SAFETY-RELATED MAINTENANCE UNIT 2

GROUP MECHANICAL (CONT'D)

MONTH JANUARY YEAR 1979 MALMJNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Unit II Containment 2-IC-78-159 10/20/78 Worn teflon seats Equalizing ball valve Replaced valve seals Emergency Air-Lock leaking by 22 Charging Pump 0-78-2062 6/25/78 Vibration fatigue Weld failure on Y section Performed weld Suction Header of suction piping repairs Unit II Containment M-78-2451 10/6/78 Sheared cam follower Door would not open Replaced cam Personnel Hatch correctly follower 22 Charging Pump 0-78-4039 12/6/78 End of natural life Primary packir,g leak Repacked pump (Packing) 21 Charging Pump 0-78-4038 12/6/78 End of natural life Primary packing leak Repacked pump and (Packing) replaced one scored plunger.

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SAFEfY-RELATED MAINTENANCE UNIT 1&2 GROUP IAC MONTH JANUARY YEAR 1979 MALMJNCTION f,YSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Safety Injection System, 0-78-2237 7/11/78 2-LY-4142 defective Oscillating current signal.

Replaced 2-LY-4142 Refueling Water Tank spurious alams at 2C08 Level Current Relay 2-LY-4142

  1. 21 Pressurizer Pres-0-78-3909 11/24/78 2-E/E 102C defective ESFAS channel ZF pres-Replaced 2-E/E sure Voltage Relay surizer pressure signal 102C 2-E/E 102C low
  1. 21 Steam Generator 0-78-3811 11/13/78 2-E/E-Irl',A defective ESFAS channel ZD generator Replaced.2-E/E-1013A Pressure Voltage pressure signal low Relay 2-E/E 1013A
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