ML19291C187

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Monthly Operating Rept for Dec 1979
ML19291C187
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 01/15/1980
From: Merson S
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19291C185 List:
References
NUDOCS 8001230091
Download: ML19291C187 (17)
v • d • e


Text

'

OPERATING DATA REPORT DOCKET NO. 3C-117 DATE 1/15 / ' "

COSIPLETED BY '-

-rson TELEPHONE l-2 5--5 2W OPERATING STATUS Calvert Cit'fs "o.

1 Notes

1. Unit Name:
2. Reporting Period:

"ce~har-1"7"

' ~ ' ' '

3. Licensed Thermal Power (51Wt):

" L'

4. Nameplate Rating (Gross SIWE):

$. Design Electrical Rating (Net 31We):

6. Siaximum Dependable Capacity iGross 31Wel:

MO

7. Maximum Dependable Capacity (Net 31We):
8. If Changes 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):

' ' " ' ~ " I ' " a

10. Reasons For Restrictions,1f Any: "' '.

-"etor in n"o ra "i n ~

'"'a" fore

'l r e  : c t i o n at s,--<ms in,dc duo to imo-ual so zer c t s trib'ition of t' e co re.

8 This Month Yr.-to-Date Cumulative ND 7M-iC 763-

11. Hours in Reporting Period
  • ^

' ' 3 3 I "'

'2*"3'"

12. Number Of Hours Reactor Was Critical

'uO 10 5

13. Recctor Reserve Shutdown Hours
14. Hours Generator On Line 7" C

'.137.0 31.702.o

15. Urut Resene Shutdown flours
16. Gross Thermal Energy Generated (MWH)

?"

117 6

!LP M7 '--

7 ' lif -

17. Gross Electri-al Energy Generated (MWH) 3T N 02' D 5 2'-

12 W

18. Net Electrical energy Generated (MWH) 313'51I

". N,21 2 3, /,2. "

19. Unit Senice Factor O'0 0 7" 1 77-
20. Unit Availability Factor n'r. c m.3 7.<
21. Unit Capacity Factor (Using MDC Net)

"I

  • 1 71-a"
22. Unit Capacity Factor il'3ing DER Net) 0-l' 1
23. Unit Forced Outage Rate
24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Eacht:

No. 1 'i n.t is < c h e.iule for a 1-vee 2 clanned cutv e startin-1/'5 /a until am ron:-

m ta!

2/1?'

~"! ' ~o C i f ica tion s re uired 5v " . G.

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

Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1791 225

- ] ^o g-o' of77) so on so o91 e

=

OPERATING DATA REPORT DOCKET NO.

~

~

DATE /i-C051PLETED BY eran TELEPHONE._M'-! T--3 2L OPERATING STATUS C21 " ' C'l i *

'o - 2

1. Unit Name:
2. Reporting Period:

Co r -

l' 7'

' 7

3. Licensed Thermal Power (51Wt):
4. Nameplate Rating (Gross SIWE):
5. Design Electrical Rating (Net AlWe):
6. Sf aximum Dependable Capacity IGross alWe):
7. Sf aximum Dependable Capacity (Net SIWE):
8. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report. Give Reasons:
9. Power Level To Which Restricted. If Any (Net SIWE):
10. Reasons For Restrictions. If Any:

This Nionth Yr.. o-Date Cumulative

11. Hours In Reporting Period

~?

12. Number Of Hours Reactor Was Critical
  1. L'

'Li.'

13. Reactor Reserve Shutdown Hours 1'1.7

-13.1

14. Hours Generator On.Line S

t

.P"7

. ',x

15. Unit Resene Shutdown ilours
16. Gross Thermal Energy Generated (51WH)

~?

'~ ** * '

-- 'i-. 11-

17. Gross Electrical Energy Generated (MWH)

' '.2

- m

~

r

18. Net Electrical Energy Generated (5tWH)

LL',

19. Unit Senice Factor

'1

-~.

' ~

77-13

20. Unit Availability Factor
21. Unit Capacity Factor (Using StDC Net) 7' 7
22. Unit Capacity Factor iUsing DER Net) 3
23. Unit Forced Outage Rate

' i

24. Shutdowns Scheduled Over Next 6 Stonths IType. Date and Duration of Each):

1/ *.1

" or 2 - l a r r. e - 0::, c to

~^

  • "' - n:

,--te' cut yr 2e vice it 1

1 ' o

"'I Odiff C1 tic"S TC 7 2irCd D

""C.

0 0.U) A C C 'T 300 OI T 2 0 '.' ? " t0 3 0 T '.'i C 0 15

25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status iPrior to Commercial Operation):

Forecast Achieved INITIAL CRITICA LITY INITIAL ELECTRICITY COM\\tERCIAL OPERATION 22g

I UNIT SilUTDOWNS AND POWER REDUCTIONS DCCKET NO.

,,,g

.q UNIT NAME DATE 1/15 4

"d COMPLETED BY "-

""r<<"

REPORT MONT11 "er"'d.e r,

1,,7 y

- LEPilONE % 4

'N Um,2

~___

)

Em=J c

3E 3

j YE Licensee h

h, Cause & Corrective

(<-,)

-E E2 2

5 Event

r. T a TJ Action to No.

Date NM S

j@

d f., d =

Report *r iE 0 Prevent Recurrence e

v no c$

5 p

/% 15 7o1102:

l' 744.0 11 4

'l//

IM:

". W '7 l'orced reductions to v.irious t o.id s b

due to unergual pover dist ribut f on.

Nso N

N I

2 3

4 N

F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A-Fquipment Fadure(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) Fde(NUREG-D-Regulatory Restriction 41:on t li u.i t i on 0161)

E-Operator Training & l.icense Examination

,,0.

i m.,inc, ;on F-Administ rative 5

"I'I'"

G-Operanonal E:ror (Explain)

Exhibit I - Same Source (9/77)

Il Ot her ( E xplain)

  • -I I '

UNIT SilUTDOWNS AND POWER REDUCT,,NS DOCKET NO.

UNIT NAME calvert <, t i t t -..,

DATE 1 / l ' ' '"

.. n.

.e r w n REPORT MONT11 '"C '" I" r, I.r 7..

COMPLETED BY 9 g _ q, _.,,3 t g (M

k-8 1

jg 3

h E.;

Licensee

[c-8, 4

Cause 1 Corrective N..

Date g

3g 4

.2 s y Event g?

g3 Action to g

Q =-

y

z
  • c Report 2r ML O

s t.c Pievent Recurrence e

o is v

5 c=

D 7 9_ ] p' 7o1110 l'

1h 4 6

l.

M/'

W P

reactor coolant p ump s,.

P 7"-1" 741210 IU

'j jg a rr 'ci 7 O ve rnpee< t trip test on the turbine.

3 70-20 191?l) 61.3 B

5 M/A ll

. 7. 'G'  ?

To con htC L power coef f ic Nut roea n u re-mente.

79-11 7"1117 l'

51.o n

/

'/ A C'Zuz h cotubic t pouer coefficient iaea s u r e-r.:e n t. s.

1

~:s

--I 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions N S: Scheduled A-Equiprnent Failure (Explain) 1 Manual for Preparation of Data fx)

B-Maintenance of Test 2-Manual Scram.

Entry Stects for Licensee w

C Refueling 3 Autoin.itic Scram.

Event Reporn (LER) File (NUREG-D.Regulati ry Restriction 4 Continnaticu 0161) 1:-Operator ' raining & License Exainination bRe,lucrton F Adnunir s.:ive

"--O t h e r 5

G-Oper... mal Es ror (Expl.nn)

Exhibit 1 - Saine Source (9/77)

Il-Othes (Explain)

AVERAGE DAILY UNIT POWER LEVEL 3C-317 DOC!;ET NO.

Calver: Cliffs il DATE 1/15/EC COMPLETED BY TELEPHONE 'OI-l'LW MONTH w e-5er. 1('70 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(Mwe. Net 3 346 377 g

2 W

3g un 552 3

19 160 553 4

20 353 551 3 f.9 5

3g 6

W 22 15 ';

7 55*

23 333 8

35L 24 15A 35*

9 S

10 311 26 15" 1I 375 27 3 5 t.

12 175 28 135 353 13 29 3 7 '.

3,' c, 14 30

~

15 176 3

l'19 17 16 INSTRUCTIONS On this format. list the average daly unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) op d

l, 1791 229

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 30-31

calvert Cliffs.i2 UNIT I/15/50 DATE COMPLETED BY 3. D. '!erson TELEPHONE 301-?34-5?ce MONTil N C ' ~ h " + 107" DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(ywe. Net) 6C0 3

37 7

2 18 7"

3 19 4

20 350 Et0 21 L7 nu 6

22 7

1"6 23

'35 03 363 8

24 313 bi; 3 9

25 10 61' 26

?01 11 77L 362 27 CL SEI 12 28 13 29 962 M'

14 30 000

'26 5 15 31 16 61' INSTRUCTIONS On this fortnato list the average daily unit power lesel in MWe Net for each day in the reporting month. Compute to the nearest whole rnegawatt.

(9/77) 1791 230 o~ b "o2 y 3 All

=

_ww

1/9/80 REFUELING INFORMATION REQUEST 1.

Name of Facility:

Calvert Cliffs Nuclear Power Plant, Unit No.1 2.

Scheduled date for next Refueling Shutdown:

September 5, 1980**

3.

Scheduled date for restart following refueling:

October 16, 1980**

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 pr: posed licensing action and supporting infonnation.

July 19, 1980**

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 assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 217 (b) 364 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 report.

1791 231

?

1/9/80 REFUELING INFORMATION REQUEST 1.

Name of Facility: Calvert C?iffs Nuclear Power Plant, Unit No. 2 2.

Scheduled date for next refueling shutdown:

November 1, 1980**

3.

Scheduled date for restart following refueling: December 11, 1980**

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.

September 11, 1980**

6.

Important licensing considerations associated with refueling.

None, reload fuel will be identical to that reload fuel inserted in the pervious cycle.

7.

The number of fuel assemblies (a) in the core and (b) in the Spent Fuel Storage Pool.

(a) 217 (b) 364 Spent Fuel Pools are conmon 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 Information has changed since last report.

1791 232

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE-DECEMBER 1979 12/1 At the beginning of this reporting period, Unit 1 was operating at 495 Mwe with the reactor at 60% power, power being limited pending analysis of the effectiveness of the lithium addition of the reactor coolant in correcting the power distribution anomaly. At 0600 load was increased to 585 FNe.

12/10 At 2000 load was reduced to 415 the for further analysis of the anomaly, 12/18 Load was reduced to 395 fNe at 1000 to remove feedwater heaters 13B-14B-153 from service due to a tube leak in 133 feedwater heater.

12/30 Reduced load to 235 Mwe at 1830 to allow repairs to 13 Condensate Pump.

12/31 Increased load to 395 'Ne at 0045. At the end of this reporting ceriod, Unit I was operating at 385 FNe witn the reactor at 50%

power, centinuing further testing and analysis of the pcwer distribution ancmaly.

1771 233

SUMYARY OF UNIT 2 OPERATING EXPERIENCE-DECEMBER 1979 12/1 At the beginning of this reporting period, Unit 2 was still shutdown in its second scheduled refueling outage.

12/2 Started reactor coolant system heatup at 1128.

12/3 Ccmpleted reactor coolant system heatup at 0440.

12/4 The reactor was brought critical at 0317. The reector was manually trippped at 1521 due to Tcold dropping below the 1imit for critical operation.

12/5 At 0110 the reactor was brought critical.

12/6 Paralleled the unit at 1623 and began increasir.g load to 50%

power to conduct physics tests.

12/11 At 0400, load was increased to 805 Mwe. Load was reduced at 1230 to 705 Mwe to repair turbine goverr.or valve di and for reroval of condensate pump suction strainers.

12/12 Increased load to 875 Mwe at 0200. At 0700 lead was reduced to 855 Ne to repair 25A feedwater heater.

Increased load to capacity (885 "we) at 1400.

12/15 Reduced load to 635 Ne at 0215 to corduct power coefficient measurements.

12/18 Increased load to 860.Ne a t 0800.

12/19 At 0755 reduced load to 785 Mve to investigate salt water leakage into the main condenser. Af ter plugginc one condenser tube, load was increased to Capacity (885 Ne) at 1900.

12/22 Started reducing load to 765 "we at 2300 for main turbir.e valve tes ti ng.

1 2/ 23 Resumed full lead creration (395 "we) at 0700.

1 2/31 At the end of this rerortir.g cer iod, Unit 2 was ocerating at 895 %e with the reactor at 100% power.

1791 234

SAFETY-RELATEC MAINTENANCE UNIT I

GROUP I&C MONTil DECEMBER YEAR 79 MALFUNCTION SYSTFM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

  1. 12. Diesel Generator 0-79-4039 1/2/79 Temperature controller Damper would not Adjusted tempera-Room / Recirculation fulcrum was out of operate as designed ture controller Air Damper Controller adjustment, caused fulcrum 1-TC-5434 by vibration Engineered Safety 0-79-4430 11/29/79 Defective signal Output voltage signal Replaced 1-EE-1023C Features Actuation Isolator 1-EE-1023C was lower than the System /#12 Steam other channels ).1 Generator Isolation volt deviation Signal, Channel ZF, 1

1023C Reactor Protection 0-79-4305 11/23/79 Defective signal Output voltage Replaced 1-EE-5313C System / Channel "C"

isolator 1-EE-5313C d tviation >.1 VDC

{}j Containment Pressure rs)

['y

  1. 11 Diesel Generator 0-79-4169 11/20/79 Damper was disengaged Damper would not Reconnected and Room Exhaust Damper from operator /also air shut in auto adjusted damper /and Operator. 0-SV-5429 leaks on tubing of replaced air tubing operator to the operator i

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9 SAFETY-RELATED f1AINTENANCE UNIT II GROUP I&C MONTil DECEMBER YEAR 79 6

MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Safety Injection System 0-79-4315 11/23/79 flounting bracket for Position indication Mounted bracket Valve 2-CV-638 Position position switch was shows intermediate properly and adjust-Indication installed improperly when valve is open ed position switch Safety Injection Q-79-4314 11/23/79 Position arm out of Position indication Adjusted position System Valve 2-CV-621 adjustment shows intermediate arm to mate with Position Indication when valve is shut position switch

  1. 22 Emergency Core 0 '9-3906 11/12/79 Position arm out of Position indication Adjusted position Cooling System Pump adjustment on switch shows intennediate ann on switch Room Air Cooler when valve is open Outlet Valve Position Indication 2-CV-5177 x1

_j$

East Penetration IC-79-2082 8/29/79 Defective transmitter Transmitter output Replaced Room Pressure was not repeatable transmitter y

Transmitter tea 2-PT-5277 N

SAFETY-RELATED MAINTENANCE UNIT II GROUP IAC MONTH DECEMBER YEAR 79 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Engineered Safety 0-79-1959 7/17/79 Module meters were Greater than.1 VDC Calibrated meters Features Actuation out of calibration deviation between System / Containment channels Pressure Channel ZD and ZF Fire System Contain-IC-79-2159 11/21/79 Limit switches out Valve would not close Adjusted limit ment Isolation Valve of adjustment tight enough to pass switches on valve 2-MOV-6200 local leak rate test

  1. 12-Control Room Air 0-79-4019 10/26/79 Defective pressure Gauge readinq high Replaced pressure

-a Conditioning Com-gauge gauge

-c) pressor / Discharge Gauge N

tra co

  1. 21 Emergency Diesel 0-79-4007 10/25/79 011 leak at fittings 011 leak Replaced fittings Generator / Engine Oil for pressure instru-ment

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3

t'ONTHLY OPEPATING REPORT UNIT I CECEMSER 1979 MECHAflICAL MAINTENANCE During April, June, July, and August of 1979, tne anchoring systems of six hundred eighty-four pipe hangers were repaired per IE Bulletin 79-14.

1791 240

MONTHLY OPERATIN3 REPORT UNIT II DECEMBER 1979 MECHANICAL MAINTENANCE During August, September, October, November, and December of 1979, the anchoring systems of fcur hundred forty-two pice hangers were repaired cer IE Bulletin 79-14.

1791 241

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