ML19274E236

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Monthly Operating Rept for Feb 1979
ML19274E236
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 03/15/1979
From: Merson S
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML15261A044 List:
References
NUDOCS 7903210012
Download: ML19274E236 (13)
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Text

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OPERATLNG DATA REPORT DOCKET NO. 50-317 DATE 3/14/79 C05tPLETED BY S.D.varson TELEPHONE 301-23h-52h0 OPERATING STATUS

1. Unit Name: C $1 va d f'1i efa h 1
2. Reporting Period: February. 1979
3. Licensed Thermal Power (StWt): 2700
4. Nameplate Rating (Gross 5tWe): 910
5. Design Electrical Rating (Net S!We): Ob5
6. Maximum Dependable Capacity (Gross SIWE): 8h5
7. Staximum Dependable Capacity (Net StWe): 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 5tWe):

ha

10. Reasons For Restrictions. If Any: N/A This Month Yr..to.Date Cumulative
11. Hours In Reporting Period 072 leb1b 33sb21
12. Number Of Hours Reactor Was Critical 672.0 997.4 97.086.1
13. Reactor Reserve Shutdown Hours 0.0 122.7 1.01 6.1
14. Hours Generator On.Line 672.0 980.8 26[.424.8
15. Unit Reserse Shutdown flours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (StWH) 1,710,7hl.6 2.h00.871.6 63.671.076.0 -
17. Gross Electrical Energy Generated (SIWH) 449.hn1 , _ .

77A loo 21 'A0 I 41'

18. Net Electrical Energy Generated (5tWH) 535'.h87 738.661 20'.595'55
19. Unit Service Factor 100.0 69.1 79.h..
20. Unit Availability Facto, 100.0 69.3 79.h
21. Unit Capacity Factor (Using SIDC Net) 96.h 6h.h 7h.6
22. Unit Capacity Factor (Using DER Net) 9h.3 61.7 71 . 4
23. Unit Forced Outage Rate 0.0 10.7 8_8
24. Shutdowns Scheduled Over Next 6 Stonths (Type. Date.and Duration of Each):

' Calvert Cliffs No.1 is scheduled for a olanned outage startirm Armil 91_ 1979; and will be six weeks in duration for general incoection and refueling.

25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units In Test Status (Prior to Commercist Operationi: Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY C0515tERCIAL OPERATION 79032100Ia_ (9/77)

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OPERATLNG DATA REPORT DOCKET NO. 50-318 DATE ._3/14/79 COMPLETED BY S.D.Merson TELEPHONE 301-23h-52h0 OPERATING STATUS Notes

1. Unit Name: Calvert 014 ffa h- ,
2. Reporting Period: February. 1979
3. Licensed Thermal Power (MWt): 9700
4. Nameplate Rating (Gross MWe): 911
5. Design Electrical Rating (Net MWe): 8h6
6. Maximum Dependable Ca,,acity (Gross MWe): Oh5
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,if Any (Net MWe): None
10. Reasons For Restrictions,If Any: N/A This Month Yr.-to-Date Cumulative
11. Hours In Reporting Period 672 1.h16 16.776
12. Number Of Hours Reactor Was Critical 672.0 1.296.1 1h 91A A
13. Reactor Reserve Shutdown Hours 0.0 0,n 219.h
14. Hours Generator On Line 65h.h 1.1%.3 11.996.1
15. Unit Reserse Shutdown flours 0.0 0.0 O.O
16. Gross Thermal Energy Generated (MWH) 1.703.496.8 1.011_98h R 31. Roc . 7m _b

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17. Gross Electrical Energy Generated (MWHI 571.159 _ _ . 1.013'.083 li'.267'.is<

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18. Net Electrical Energy Generated (MWH) 5h7,008 967,029 10.735'.058
19. Unit Service Factor 97 h 83.6 81.le
20. Unit Availability Factor 97.h 83.6 83.h
21. Unit Capacity Factor IUsing MDC Net) 100.4 8h.3 7o_n
22. Unit Capacity Factor IUsing DER Nety 96.3 80.8 76.7
3. Unit Forced Outage Rate 0.0 1A c: _ R
24. Shutdowns Scheduled Oser Next 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 Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION _

(9/77)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.40-117 UNIT Calvert Cliffs No.1, DATE 1/1</79 COMPLETED BY S.D.Merson TELEPIIONE 101-21h-62h0 t

MONTil February,1979 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (Mwe-Net I 808 17 806 2 811 18 6h8 3 A19 39 801 4 81h 20 810 5 817 21 808 6 771 22 811 7 812 - 23 818 8 76h 24 8h1 9 #, 706 25 8hl 10 79h 26 8h3 II , 796 27 8h3 12 758 28 8h2 13 NO 29 14 798 3o is 813 3 16 809 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) i

s., . .

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-318 UNIT Calvert Cliffs #2 DATE 3/19/79 COMPLETED BY S.D.Merson TELEP110NE 101-21h-42h0 MONT11 February, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

85h 37 %5 2 842 18 8h6 3 840 39 8hh 4 8h9 :o 8h5 5 853 21 8hh 6 852 22 8h6 7 853 23 8h9 8 852 24 863 9 8hl 25 195 10 816 26 738 II 806 27 844 12 771 28 848 13 799 29 14 A9)' 30 15 8h4 31 16 bN LNSTRUCTi3NS On this format, list the average daily unit power levelin .\lWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

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DOCKET NO. Cn-31R UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Calvert Cliffs No. 2 DATE 3/15/79 COMPLETED BY S.D.Mersen REPORT MONT11 Fehnmnr; 1979 TELEPilONE 101-93h <9hn c

.! E 3i; y .E 3 Licensee Eg {wl, Cause & Corrective No. Date h 3g 2 ~5 Event g { Action to H jE 5 jgg Repost er mo Preveni Recurrence 6

79-2 790225 s 17.6 A 1 N/A CH VALVE Scheduled Outage to Repair a Leak-ing Feedwater Check Valve.

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 Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Ot her (Explain) 0161) 1:-Operator Training & License Examination F Administrative 5 G-Operational Eirur (Explam) Exhibit I - Same Source 19/77) Il-Ot her (E xplain)

3/8/79 REFUELING INFORMATION REOUEST

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 15, 1979 **
4. Will refueling or resumption of operation thereaf ter 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. The reload will include one SCOUT demonstration assembly and one PROTOTYPE CEA.

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) 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

    • Infonnation has changed since last monthly report.

3/8/79 REFUELING INFORMATION REQUEST

1. Name of Facility Calvert Cliffs Nuclear Pcwer 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 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.

July 6, 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 assmblies (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.

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

SU!HARY OF UNIT 1 OPERATING EXPERIEtlCE FEBRUARY 1979 2/1 At the beginning of this reporting period, Unit I was operating at 843 Ifde with the reactor at 97% power, reactor power being limited by the Environmental Technical Specification (ETS) 10 F limit on main condenser circulating water 4 T.

2/6 Load was decreased to 679 ffde at 1004 to investigate salt water leakage into the main condenser. Load was increased to capacity (850 MWe) at 2100 after the leak. disappeared. Reactor power was limited to 97% due to the ETS 10 F limit on main condenser circulating water 4 T.

2/8 Reactor Power was decreased to 81% due to a failure of the plant computer which resulted in a loss of the incore instrumentation monitoring system as required by the Technical Specifications.

2/9 Load was increased to 845 file at 1730 following repairs to the plant computer. Load was reduced to 830 ffde (2560 MWth reacto power) at 1800 after questions were raised by the NRC concerning certain credits taken in the ECCS analysis for a small line break which were used in the 2700 f4Wth license submittal.

2/12 Load was reduced to 710 ffde at 1505 to investigate salt water leakage into the main condenser.

2/13 Load was increased to capacity (831 RIe) at 1831 after plugging 3 tubes.

Reactor power was limited to 94% pending reassessment of the ECCS analysis for a small line break.

2/14 Load was increased to 850 ffde at 1915 after receiving satisfactory results to the reassessment of the ECCS analysis for a small line break. Reactor power was limited to 97% due to the ETS 10 F limit on main condenser circulating water o T.

2/18 At 0130 control element assembly (CEA) 44 dropped into the core. Reactor power was decreased to less than 70% as required by the Technical Specifi-cations. CEA 44 was withdrawn to its group at 0610 and began increasing load to capacity. At 1017 CEA 57 dropped into the core. Reactor power was held at less than 70% as required by the Technical Specifications.

CEA 57 was withdrawn to its group at 1045 and began increasing load to capacity. At 1627 four incore detector linear heat rate alarms went into alam. Reactor power was reduced to 85% to prevent exceeding Technical Specification limits.

2/19 Load was increased to capacity (848 ffde) at 0730. Reactor power was limited to 95% due to the ETS 10*F limit on main condenser circulating water A T.

2/23 Auendnent 36 to the Technical Snecifications which authorized an increase to 12 F the ETS limit for the main condenser circulating water 4 T, to allow 3

a 24-month environmental impact study was received. Load was increased to 383 Mle at 2300.

2/23 At the end of this reporting period Unit 1 was operating at 885 ff.le with the reactor at 100% power.

SUtHARY OF UNIT 2 OPERATING EXPERIENCE FEBRUARY 1979 2/1 At the beginning of this reporting period Unit 2 was operating at 894 tWe with the reactor at 100% power.

2/9 Load was reduced to 853 fWe (2560 tWth reactor power) at 1800 after questions were raised by the NRC concerning certain credits taken in the ECCS analysis for a small line break which were used in the 2700 lWth license submittal.

2/11 Load was decreased to 769 fWe at 1040 for turbine control valve testing.

Load was returned to capacity (853 fWe) at 1600. Reactor power was limited to 94% pending reassessment of the ECCS analysis for a small line break.

2/12 Load was decreased to 720 fWe at 1428 to investigate salt water leakage into the main condenser.

2/13 Load was increased to capacity (852 tWe) at 0400 after plugging 1 tube.

Reactor power was limited to 94% pending reassessment of the ECCS analysis for a small line break.

2/14 Load was increased to 883 PWe at 1930 after receiving satisfactory results to the reassessment of the ECCS analysis for a small line break. 8 Reactor power was limited to 98% due to the Environmental Technical Specification (ETS) 10 F limit on main condenser circulating water o T.

2/23 Amendment 19 to the Technical Specifications which authorized an increase to 12*F the ETS limit for the main condenser circulating water A T to allow a k4 month environmental impact study was received. Load was increased to 899 IWe at 2200.

2/25 Began decreasing load at 0430 for a scheduled maintenance outage; the Unit was taken off line at 0736. The reactor remained critical.

2/26 The unit was paralleled at 0112. Full load operation (893 iWe) resumed at 0630.

2/28 At the end of this reporting period Unit 2 was operating at 895 fWe with the reactor at 100% power.

SAFEfY-REI.ATED MAINTENANCE ';

UNIT I MECHANICAL GROUP MON'rH FEBRUARY YEAR l979 MAI.FTJNCTION SYf7PEtt OR COMPONENT MR HO. - DATE CAllSE RESULT CORRECTIVE ACTION Containment Personnel M-79-121 1/10/79 Geneva plates out of Inner door jammed open Re-adjusted geneva Hatch adjustment plates 1-SI-463 SI Leakoff to IC-78-023 1/26/78 Seat was pitted Excessive seat leakage Lapped disc and plug RWT l-SI-247 Loop Isolation M-79-104 1/2/79 Seat was pitted Leakage thru valve Lapped disc and plug Check Valve

  1. 11 Charging Pump 0-78-4105 12/12/78 Ruptured bladder Desurger inoperable Replaced bladder Desurger 1-CV-5156 Service Water 0-78-4026 12/4/78 Valve operator not Valve was stuck open Re-aligned valve to HX,22 Salt Water Outlet properly centered on valve operator valve

SAFETY-RELATED MAINTENANCE ..

UNIT II GROUP MECHANICAL MONTH FEBRUARY YEAR l979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Containment Personnel M-78-2283 7/8/78 Broken cam follower ., Inner door wouldn't open Replaced cam Airlock . geneva plates needed followers, geneva timing plates 22 Charging Pump 0-78-2062 6/25/78 Excessive vibration lleld leak at "Y" Performed weld Suction Header immediately down stream repairs HC-16-2004 of 2-CV-501 23 Charging Pump 0-78-3833 11/16/78 Ruptured bladder Desurger inoperable Replaced bladder Desurger '

22 Containment Cooler 0-78-2302 7/16/78 Worn bearings Excessive noise, motor Replaced bearings was incorrect,-blade pitch tripped on overload adjusted blade pitch

SAFFTY-ilELATED MAINTENAliCE , ,'

UNIT I II GROUP ELECTRICAL, I & C FEBRUARY YEAR 1979 touTil MALFUNCTTON SYfirEM OR C0f4PO!!ENT MR 110. - DATE CAUSE RESULT _ _

C0RRECTIVE ACTION Safety Injection System 0-79-141 1/15/79 Fuse blown in 1-LY-311A Narrow. range level Replaced fuse and 1-LY-321A indication failed Safety Injection Tank Level Indication for llA & llB Safety Injection System 0-79-118 1/16/79 Fuse blown in 1-LY-4142 Narrow range level failed, Replaced fuse

  1. 11 Refueling Water low indication Tank ESFAS Actuation Logic 0-78-4217 1/19/79 Defective SI AS - A2 Spurious SIAS trips Replaced logic Cabinet 1C67L Logic Module module
  1. 21 Charging Pump 0-79-316 1/26/79 Blown fuse and burned Charging pump would not Replaced fuse and closing coil on breaker start closing coil 52-2115

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